WorldWideScience

Sample records for radioactive surface contamination

  1. Radioactive surface contamination monitors

    International Nuclear Information System (INIS)

    Aoyama, Kei; Minagoshi, Atsushi; Hasegawa, Toru

    1994-01-01

    To reduce radiation exposure and prevent contamination from spreading, each nuclear power plant has established a radiation controlled area. People and articles out of the controlled area are checked for the surface contamination of radioactive materials with surface contamination monitors. Fuji Electric has repeatedly improved these monitors on the basis of user's needs. This paper outlines typical of a surface contamination monitor, a personal surface contamination monitor, an article surface contamination monitor and a laundry monitor, and the whole-body counter of an internal contamination monitor. (author)

  2. Decontamination of radioactively contaminated surfaces

    International Nuclear Information System (INIS)

    1986-10-01

    By this standard objective conditions to evaluate and test the ease of decontamination of surfaces under laboratory conditions are to be laid down. Ease of decontamination in this context denotes the summed-up effect of two material properties: a) the capacity of the material for retaining radioactive substances at its surface; b) the ease with which these substances are given off again in the course of cleaning processes. (orig./HP) [de

  3. Development of radioactive surface contamination monitor

    International Nuclear Information System (INIS)

    Hashimoto, Tadao; Hasegawa, Toru; Fukumoto, Keisuke; Ooki, Yasushi

    2008-01-01

    In the radiation facilities such as nuclear power plants, surface contamination of the people accessing or articles conveyed in and out of the radiation controlled areas is detected and monitored by installing contamination monitors at the boundary of controlled areas and uncontrolled areas against the expansion of the radioactive materials to out of the facilities. It is required for the surface contamination of articles to be tightened of control criteria as 'Guidelines for discrimination ways of nonradioactive waste (not classified as radioactive waste) generated from nuclear power plants' (hereinafter referred to as 'the Guideline') was established by the Nuclear and Industrial Safety Agency of the Ministry of Economy, Trade and Industry in August, 2005. It predicts that the control criteria of monitors other than article monitors are also tightened in the future. Fuji electric has been fabricating and delivering surface contamination detecting monitors. Now we are developing the new contamination monitor corresponding to the tightening of the control criteria. 'Large article transfer monitor', 'Clothing monitor' and 'Body surface contamination monitor' are introduced in this article. (author)

  4. Process for cleaning radioactively contaminated metal surfaces

    International Nuclear Information System (INIS)

    Mihram, R.G.; Snyder, G.A.

    1975-01-01

    A process is described for removing radioactive scale from a ferrous metal surface, including the steps of initially preconditioning the surface by contacting it with an oxidizing solution (such as an aqueous solution of an alkali metal permanganate or hydrogen peroxide), then, after removal or decomposition of the oxidizing solution, the metallic surface is contacted with a cleaning solution which is a mixture of a mineral acid and a complexing agent (such as sulfuric acid and oxalic acid), and which preferably contains a corrosion inhibitor. A final step in the process is the treatment of the spent cleaning solution containing radioactive waste materials in solution by adding a reagent selected from the group consisting of calcium hydroxide or potassium permanganate and an alkali metal hydroxide to thereby form easily recovered metallic compounds containing substantially all of the dissolved metals and radioactivity. (auth)

  5. Bonding of radioactive contamination. IV. Effect of surface finish

    International Nuclear Information System (INIS)

    Rankin, W.N.

    1983-01-01

    The mechanisms by which radioactive contamination would be bonded to a DWPF canister are being investigated. Previous investigations in this series have examined the effects of temperature, oxidation before contamination, and atmosphere composition control on the bonding of contamination. This memorandum describes the results of tests to determine the effect of special surface finishes on the bonding of contamination to waste glass canisters. Surface pretreatments which produce smoother canister surfaces actually cause radioactive contamination to be more tightly bonded to the metal surface than on an untreated surface. Based on the results of these tests it is recommended that the canister surface finish be specified as having a bright cold rolled mill finish equivalent to ASTM No. 2B. 7 references, 3 figures, 3 tables

  6. Worker exposures from recycling surface contaminated radioactive scrap metal

    International Nuclear Information System (INIS)

    Kluk, A.; Phillips, J.W.; Culp, J.

    1996-01-01

    Current DOE policy permits release from DOE control of real property with residual levels of surficial radioactive contamination if the contamination is below approved guidelines. If the material contains contamination that is evenly distributed throughout its volume (referred to as volumetric contamination), then Departmental approval for release must be obtained in advance. Several DOE sites presently recycle surface contaminated metal, although the quantities are small relative to the quantities of metal processed by typical mini-mills, hence the potential radiation exposures to mill workers from processing DOE metals and the public from the processed metal are at present also a very small fraction of their potential value. The exposures calculated in this analysis are based on 100% of the scrap metal being processed at the maximum contamination levels and are therefore assumed to be maximum values and not likely to occur in actual practice. This paper examines the relationship between the surface contamination limits established under DOE Order 5400.5, open-quotes Radiation Protection of the Public and the Environment,close quotes and radiation exposures to workers involved in the scrap metal recycling process. The analysis is limited to surficial contamination at or below the guideline levels established in DOE Order 5400.5 at the time of release. Workers involved in the melting and subsequent fabrication of products are not considered radiation workers (no requirements for monitoring) and must be considered members of the public. The majority of the exposures calculated in this analysis range from tenths of a millirem per year (mrem/yr) to less than 5 mrem/yr. The incremental risk of cancer associated with these exposures ranges from 10 -8 cancers per year to 10 -6 cancers per year

  7. Radioactive air and surface contamination in Czechia and Slovakia

    International Nuclear Information System (INIS)

    Rumyantsev, V.V.

    1992-01-01

    Data are presented on the radioactive substance effluents into the environment in conditions of NPP normal operation and on the air contamination by 85 Kr due to operation of the European and Soviet plants for reprocessing spent nuclear fuel. Data are given on the dosage of the Czechoslovakia population due to the Chernobyl NPP accident

  8. Levels of surface contamination with radioactive materials at workplaces of nuclear research centre at Rez

    International Nuclear Information System (INIS)

    Hoelgye, Z.; Nemcova, I.; Kasikova, M.; Popper, J.; Chysky, J.

    1983-01-01

    A hygiene supervision unit at workplaces of the nuclear Research Institute in Rez monitored on a long-term basis surface contamination with radioactive substances. Surface contamination was found at workplaces with open sources. Of the 4343 monitored places action levels were only exceeded in 13 cases. The obtained data were used for typifying workplaces with the highest level of surface contamination, to determine in certain instances the mechanism of the escape of radioactive substances from insulating facilities and to determine the rate of the spread of the radioactive substance into adjacent non-active workplaces. (author)

  9. Development of an automatic smear sampler and a polymer film for surface radioactive contamination assay

    International Nuclear Information System (INIS)

    Seo, B.-K.; Lee, K.-W.; Woo, Z.-H.; Jeong, K.-S.; Oh, W.-Z.; Han, M.-J.

    2004-01-01

    Measurement of the surface contamination by an indirect method is subject to the various kinds of error according to the sampling person and needs much time and effort in the sampling and assay. In this research, an automatic smear sampler is developed. It improved efficiency for assay work of surface contamination level achieved periodically in a radiation controlled area. Using an automatic smear sampler developed, it is confirmed that radioactive contaminated materials are uniformly transferred to smear paper more than any sampling method by an operator. Also, Solid scintillation proximity membranes were prepared for measuring the amount of radioactive contamination in laboratories contaminated by the low energy beta-ray emitter, such as 3 H and 14 C. Polysulfone scintillation proximity membranes were prepared by impregnating Cerium Activated Yttrium Silicate (CAYS), an inorganic fluor, in a membrane structure. The inorganic fluor-impregnated membranes were applied to detect the radioactive surface contamination. The preparation of membranes was divided into two processes. A supporting polymer film was made of casting solutions consisting of polysulfone and solvent, their cast film being solidified by vacuum evaporation. CAYS-dispersed polymer solutions were cast over the first, solidified polymer films and coagulated either by evaporating solvent in the solution with non-solvent in a coagulation bath. The prepared membranes had two distinguished, but tightly attached, double layers : one is the supporting layer of dense polymer film and the other results revealed that the prepared membranes were efficient to monitor radioactive contamination with reliable counting ability. For enhancement of pick-up and measurement efficiency, the membrane was prepared with the condition of different membrane solidification. The scintillation produced by interaction with radiation and CAYS was measured with photomultiplier tube. The test results showed that the prepared

  10. Radioactive contamination of some rubber or plastic surfaces by fission products. Decontamination tests

    International Nuclear Information System (INIS)

    Mestre, E.; Sautiez, N.

    1957-10-01

    With the objective of notably addressing the contamination and decontamination of gloves and floor covering, this report first presents some characteristics of contaminating radioactive materials (nature, physical and chemical condition), of contaminated surfaces (surface condition, surface nature), and of decontamination processes (physical, chemical or mechanical action). It describes the operational modality implemented to test decontamination processes on various glove or flooring materials: sample preparation, counting, decontamination, reproducibility of decontamination tests, results in terms of activity reduction. It more precisely describes the tested samples: short gloves, gloves from glove boxes, floor and wall coverings. Results are presented and discussed in terms of sample susceptibility to contamination, and of decontamination, but also for re-contamination tests after a Nab-based decontamination (susceptibility to contamination, decontamination gain)

  11. Measurement of residual radioactive surface contamination by 2-D laser heated TLD

    International Nuclear Information System (INIS)

    Jones, S.C.

    1997-06-01

    The feasibility of applying and adapting a two-dimensional laser heated thermoluminescence dosimetry system to the problem of surveying for radioactive surface contamination was studied. The system consists of a CO 2 laser-based reader and monolithic arrays of thin dosimeter elements. The arrays consist of 10,201 thermoluminescent phosphor elements of 40 micron thickness, covering a 900 cm 2 area. Array substrates are 125 micron thick polyimide sheets, enabling them to easily conform to regular surface shapes, especially for survey of surfaces that are inaccessible for standard survey instruments. The passive, integrating radiation detectors are sensitive to alpha and beta radiation at contamination levels below release guideline limits. Required contact times with potentially contaminated surfaces are under one hour to achieve detection of transuranic alpha emission at 100 dpm/100 cm 2 . Positional information obtained from array evaluation is useful for locating contamination zones. Unique capabilities of this system for survey of sites, facilities and material include measurement inside pipes and other geometrical configurations that prevent standard surveys, and below-surface measurement of alpha and beta emitters in contaminated soils. These applications imply a reduction of material that must be classified as radioactive waste by virtue of its possibility of contamination, and cost savings in soil sampling at contaminated sites

  12. Removal and treatment of radioactive, organochlorine, and heavy metal contaminants from solid surfaces

    International Nuclear Information System (INIS)

    Grieco, S.A.; Neubauer, E.D.

    1996-01-01

    The U.S. Department of Energy (DOE) is defining decontamination and decommissioning (D ampersand D) obligations at its sites. Current D ampersand D activities are generally labor intensive, use chemical reagents that are difficult to treat, and may expose workers to radioactive and hazardous chemicals. Therefore, new technologies are desired that minimize waste, allow much of the decommissioned materials to be reused rather than disposed of as waste, and produce wastes that will meet disposal criteria. The O'Brien ampersand Gere companies tested a scouring decontamination system on concrete and steel surfaces contaminated with radioactive and hazardous wastes under the sponsorship of Martin Marietta Energy Systems, Inc. (MMES) at DOE's K-25 former gaseous diffusion plant in Oak Ridge, Tennessee. The scouring system removes fixed radioactive and hazardous contamination yet leaves the surface intact. Blasting residuals are treated using physical/chemical processes. Bench- and pilot-scale testing of the system was conducted on surfaces contaminated with uranium, technetium, heavy metals, and PCBs. Areas of concrete and metal surfaces were blasted. Residuals were dissolved in tap water and treated for radioactive, hazardous, and organochlorine constituents. The treatment system comprised pH adjustment, aeration, solids settling, filtration, carbon adsorption, and ion exchange. This system produced treated water and residual solid waste. Testing demonstrated that the system is capable of removing greater than 95% of radioactive and PCB surface contamination to below DOE's unrestricted use release limits; aqueous radionuclides, heavy metals, and PCBs were below DOE and USEPA treatment objectives after treatment. Waste residuals volume was decreased by 71 %. Preliminary analyses suggest that this system provides significant waste volume reduction and is more economical than alternative surface decontamination techniques that are commercially available or under development

  13. Safety against radioactive contamination

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The ALWIT anticontamination suit is briefly described, consisting of lasting antistatic ''NDMEX III''. It was specially developed for the fire brigade who are exposed to a particular kind of contamination while carrying out radiation measurements during fire fighting, rescue and clearing up work. The ALWIT suit reliably prevents radioactive contamination of the surface of the body while wearing a breathing apparatus, independent of the ambient air. Tightly fitting cuffs on the neck, arms and legs together with zippers placed behind prevent contamination even with extreme movement. (P.F.K.)

  14. Electrolyze radioactive contamination away

    International Nuclear Information System (INIS)

    Wedman, D.E.; Martinez, H.E.; Nelson, T.O.

    1996-01-01

    The Los Alamos National Laboratory Plutonium Facility is using electrolysis to clean the surfaces of hazardous materials. In the past, contaminated metals were cleaned with concentrated acids. Although these treatments make the surfaces safer, they produce other radioactive and toxic wastes in turn. Anodic current passes through a piece of stainless steel submersed in a sodium nitrate solution, and steel dissolves at the surfaces. Surface contamination strips away along with the surface layers. The authors are using this electrolysis approach to remove plutonium and americium from stainless steel and uranium. Unlike acid washing processes, electrolytic decontamination can be accomplished quickly. Little waste is generated regardless of how much material has to be removed from the surface. Material removal is proportional to the applied current, which gives the operator control over the rate and extent of decontamination

  15. Risk assessment based on current release standards for radioactive surface contamination

    International Nuclear Information System (INIS)

    Chen, S.Y.

    1993-09-01

    Standards for uncontrolled releases of radioactive surface contamination have been in existence in the United States for about two decades. Such standards have been issued by various agencies, including the US Department of Energy. This paper reviews the technical basis of published standards, identifies areas in need of revision, provides risk interpretations based on current technical knowledge and the regulatory environment, and offers suggestions for improvements

  16. A Review of Removable Surface Contamination on Radioactive Materials Transportation Containers

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, Jr, W. E.; Watson, E. C.; Murphy, D. W.; Harrer, B. J.; Harty, R.; Aldrich, J. M.

    1981-05-01

    This report contains the results of a study sponsored by the U.S. Nuclear Regulatory Commission (NRC) of removable surface contamination on radioactive materials transportation containers. The purpose of the study is to provide information to the NRC during their review of existing regulations. Data was obtained from both industry and literature on three major topics: 1) radiation doses, 2) economic costs, and 3) contamination frequencies. Containers for four categories of radioactive materials are considered including radiopharmaceuticals, industrial sources, nuclear fuel cycle materials, and low-level radioactive waste. Assumptions made in this study use current information to obtain realistic yet conservative estimates of radiation dose and economic costs. Collective and individual radiation doses are presented for each container category on a per container basis. Total doses, to workers and the public, are also presented for spent fuel cask and low-level waste drum decontamination. Estimates of the additional economic costs incurred by lowering current limits by factors of 10 and 100 are presented. Current contamination levels for each category of container are estimated from the data collected. The information contained in this report is designed to be useful to the NRC in preparing their recommendations for new regulations.

  17. Portable instrumentation for quantitatively measuring radioactive surface contaminations, including 90Sr

    International Nuclear Information System (INIS)

    Brodzinski, R.L.

    1983-10-01

    In order to measure the effectiveness of decontamination efforts, a quantitative analysis of the radiocontamination is necessary, both before and after decontamination. Since it is desirable to release the decontaminated material for unrestricted use or disposal, the assay equipment must provide adequate sensitivity to measure the radioactivity at or below the release limit. In addition, the instrumentation must be capable of measuring all kinds of radiocontaminants including fission products, activation products, and transuranic materials. Finally, the survey instrumentation must be extremely versatile in order to assay the wide variety of contaminated surfaces in many environments, some of which may be extremely hostile or remote. This communication describes the development and application of portable instrumentation capable of quantitatively measuring most transuranics, activation products, and fission products, including 90 Sr, on almost any contaminated surface in nearly any location

  18. Application of autonomous robotics to surveillance of waste storage containers for radioactive surface contamination

    International Nuclear Information System (INIS)

    Sweeney, F.J.; Beckerman, M.; Butler, P.L.; Jones, J.P.; Reister, D.B.

    1991-01-01

    This paper describes a proof-of-principal demonstration performed with the HERMIES-III mobile robot to automate the inspection of waste storage drums for radioactive surface contamination and thereby reduce the human burden of operating a robot and worker exposure to potentially hazardous environments. Software and hardware for the demonstration were developed by a team consisting of Oak Ridge National Laboratory, and the Universities of Florida, Michigan, Tennessee, and Texas. Robot navigation, machine vision, manipulator control, parallel processing and human-machine interface techniques developed by the team were demonstrated utilizing advanced computer architectures. The demonstration consists of over 100,000 lines of computer code executing on nine computers

  19. Control of the surface radioactive contamination in the field of biological research

    International Nuclear Information System (INIS)

    Calvo, S.; Encina, A. de la; Gaspar, J.; Macias, M. T.; Sanchez, A.; Usera, F.

    2012-01-01

    The manipulation of unsealed sources in biomedical research involves significant risk of radioactive contamination. the aim of this study has been to analyze the radioactive contamination occurring in the field of biomedical research, assessing its magnitude, identifying the equipment that can be contaminated with higher probability and monitoring the evolution of the contaminations production taking into account the radioisotopes and the activities uses, and the radiation protection control applied. The data used for this study correspond to a very lengthy period of time and it have been collected in the radioactive facility, of the Centro Nacional de Biotecnologia (CSIC), a very large biological research centre that can be used perfectly as a reference for this area. The results obtained show a gradual and significant decrease in the incidence of the radioactive contamination. This is due to the optimization of radiation protection standards applied and the implementation or a systematic operational radiation protection program. (Author) 13 refs.

  20. Trench 'bathtubbing' and surface plutonium contamination at a legacy radioactive waste site.

    Science.gov (United States)

    Payne, Timothy E; Harrison, Jennifer J; Hughes, Catherine E; Johansen, Mathew P; Thiruvoth, Sangeeth; Wilsher, Kerry L; Cendón, Dioni I; Hankin, Stuart I; Rowling, Brett; Zawadzki, Atun

    2013-01-01

    Radioactive waste containing a few grams of plutonium (Pu) was disposed between 1960 and 1968 in trenches at the Little Forest Burial Ground (LFBG), near Sydney, Australia. A water sampling point installed in a former trench has enabled the radionuclide content of trench water and the response of the water level to rainfall to be studied. The trench water contains readily measurable Pu activity (~12 Bq/L of (239+240)Pu in 0.45 μm-filtered water), and there is an associated contamination of Pu in surface soils. The highest (239+240)Pu soil activity was 829 Bq/kg in a shallow sample (0-1 cm depth) near the trench sampling point. Away from the trenches, the elevated concentrations of Pu in surface soils extend for tens of meters down-slope. The broader contamination may be partly attributable to dispersion events in the first decade after disposal, after which a layer of soil was added above the trenched area. Since this time, further Pu contamination has occurred near the trench-sampler within this added layer. The water level in the trench-sampler responds quickly to rainfall and intermittently reaches the surface, hence the Pu dispersion is attributed to saturation and overflow of the trenches during extreme rainfall events, referred to as the 'bathtub' effect.

  1. Trench ‘Bathtubbing’ and Surface Plutonium Contamination at a Legacy Radioactive Waste Site

    Science.gov (United States)

    2013-01-01

    Radioactive waste containing a few grams of plutonium (Pu) was disposed between 1960 and 1968 in trenches at the Little Forest Burial Ground (LFBG), near Sydney, Australia. A water sampling point installed in a former trench has enabled the radionuclide content of trench water and the response of the water level to rainfall to be studied. The trench water contains readily measurable Pu activity (∼12 Bq/L of 239+240Pu in 0.45 μm-filtered water), and there is an associated contamination of Pu in surface soils. The highest 239+240Pu soil activity was 829 Bq/kg in a shallow sample (0–1 cm depth) near the trench sampling point. Away from the trenches, the elevated concentrations of Pu in surface soils extend for tens of meters down-slope. The broader contamination may be partly attributable to dispersion events in the first decade after disposal, after which a layer of soil was added above the trenched area. Since this time, further Pu contamination has occurred near the trench-sampler within this added layer. The water level in the trench-sampler responds quickly to rainfall and intermittently reaches the surface, hence the Pu dispersion is attributed to saturation and overflow of the trenches during extreme rainfall events, referred to as the ‘bathtub’ effect. PMID:24256473

  2. Evaluation of indigenously developed plastic scintillator sheet detector for surface radioactive contamination monitoring application

    International Nuclear Information System (INIS)

    Sahani, R.M.; Chaudhary, H.S.; Mahala, V.K.; Senwar, K.R.; Meena, J.P.

    2018-01-01

    Radioactive contamination may be caused by release of radioactivity in the environment due to accident at nuclear plant/reactor or spillage of loose radioactive materials in a laboratory. The protection of workers from potentially hazardous radiations emitted by the contaminants is a matter of prime concern. The detection of such radiations requires a monitoring system capable of measuring the level of radioactivity at the contaminated site. Plastic scintillators are widely used for large area radiation monitoring due to the ease of preparation in different shape and sizes. These detectors are sensitive to beta and gamma radiation therefore can be used for monitoring of beta and gamma contamination. In this paper, performance results of indigenously developed plastic scintillator sheet of area 800 cm 2 are reported

  3. Decontamination of radioactively contaminated surfaces - Testing of decontamination agents for textiles. 1. ed.

    International Nuclear Information System (INIS)

    1992-01-01

    The present International Standard provides an experimental method for determining the efficiency of the agents for removal radionuclides deposited on textile materials. It applies to testing the detergents which might be used in water solution for cleaning textiles contaminated by radioactive elements. It is applicable for testing the efficiency of detergents for eliminating non-radioactive dirt

  4. Radioactive contamination of some rubber or plastic surfaces by fission products. Decontamination tests; Contamination radioactive de quelques surfaces en caoutchouc ou en matiere plastique par des produits de fission. Essais de decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Mestre, E.; Sautiez, N.

    1957-10-15

    With the objective of notably addressing the contamination and decontamination of gloves and floor covering, this report first presents some characteristics of contaminating radioactive materials (nature, physical and chemical condition), of contaminated surfaces (surface condition, surface nature), and of decontamination processes (physical, chemical or mechanical action). It describes the operational modality implemented to test decontamination processes on various glove or flooring materials: sample preparation, counting, decontamination, reproducibility of decontamination tests, results in terms of activity reduction. It more precisely describes the tested samples: short gloves, gloves from glove boxes, floor and wall coverings. Results are presented and discussed in terms of sample susceptibility to contamination, and of decontamination, but also for re-contamination tests after a Nab-based decontamination (susceptibility to contamination, decontamination gain)

  5. Internal radioactive contamination treatment

    International Nuclear Information System (INIS)

    Tobajas, L. M.

    1998-01-01

    In a radiological emergency, the internal radioactive contamination becomes a therapeutic urgency and must be established as fast as possible. Just when a radioactive contamination accident occurs, it is difficult to know exactly the amount of radioactive materials absorbed and to estimate the dose received.. The decision to be taken after the incorporation of the radioactive material depends on the method and on the Radiological Protection Department collaboration. Any treatment achieving a reduction of the doses received or expected will be useful. The International Radiological Protection Commission doesn't recommend the use of the dose limit, to decide about the intervention necessity. However the LIA can be used as the reference point to establish the necessity and reach of the treatment. The object of the present work, is to introduce the general principles to carry out the internal people decontamination, under the last international recommendations. (Author) 4 refs

  6. A model to determine the radiological implications of non-fixed radioactive contamination on the surfaces of packages and conveyances

    International Nuclear Information System (INIS)

    Hughes, J.S.; Warner Jones, S.M.; Lizot, M.T.; Perrin, M.L.; Thierfeld, S.; Schroedl, E.; Schwarz, G.; Rawl, R.; Munakata, M.; Hirose, M.

    2004-01-01

    The surfaces of packages and conveyances used to transport radioactive materials can sometimes become contaminated with radioactive material. This usually occurs as a result of the transfer of radioactive material from areas in which these packages and conveyances are handled. This contamination may subsequently be transferred to transport equipment, workers and to areas accessible to the public. This can represent a significant radiation safety issue that requires careful management. The current regulatory limits for non-fixed contamination on packages and conveyances have been in use for over 40 years, and are based on a simple exposure model. However, the bases on which these limits were derived have been subject to changes, as a result of successive revisions of international recommendations. In recognition of this need for a review and analysis of the current contamination limits an IAEA Co-ordinated Research Project (CRP) on the ''Radiological Aspects of Package and Conveyance Non-Fixed Contamination'' was initiated to review the scientific basis for the current regulatory limits for surface contamination. The CRP was also to develop guidance material for evaluating the radiological significance of surface contamination to workers and the public in light of state-of-the-art research, technical developments and current transport practices. The specific objectives of the work undertaken within this multi-national CRP were, in accordance with the terms of reference: To ensure that appropriate models exist for all package types including consideration of the aspects pertinent for assessing and revising a surface contamination model for transport. To collect - where possible - contamination, operational and dosimetric data to ensure modelling consistency. To use models for assessing the limitations and optimisation of radiation doses incurred in transport operations, and to consider preventive methods for package and conveyance contamination

  7. Organization of work for prevention of propagation of radioactive contamination, for decontamination of the premise surfaces and individual protective means in case of radiation accident

    International Nuclear Information System (INIS)

    Klochkov, V.N.; Vas'kin, A.G.; Filatova, V.M.

    1995-01-01

    Radiation accident results in radioactive contamination of the surface, clothes and other property. If proper measures are taken, it will prevent propagation of contamination. Decontamination of surfaces - is a complicated and tedious process. The paper has examined the measures of organization and technical aspects of prevention of propagation of radioactive contamination. Methods of decontamination of internal surfaces of premises are demonstrated, organization of the individual protective means is determined. 9 refs

  8. Surface soil contamination standards

    International Nuclear Information System (INIS)

    Boothe, G.F.

    1979-01-01

    The purpose of this document is to define surface soil contamination limits for radioactive materials below which posting, restrictions and environmental controls are not necessary in order to protect personnel and the environment. The standards can also be used to determine if solid waste or other material is contaminated relative to disposal requirements. The derivation of the standards is given

  9. Environmental radioactivity and water supply. Pt. 3. The contamination of surface waters in Germany after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Haberer, K.

    1988-03-01

    After the reactor accident, german surface waters have been monitored in numerous positions over a long period of time. The highest concentrations of iodine 131 occurred in the lower german region of the Danube river with more than 200 Bg/l whereas the Rhine river had the lowest concentrations. The sudden rise of the radioactivity of the river water have been followed by a slower decrease but nevertheless much faster than the radioactive decay. Probably this is caused by the interaction with river sediments. For the german lakes and reservoirs it was very important whether the water masses have been stratified or not when the radioactive cloud arrived. Where this was the case, the radioactive contaminants remained predominantly in the upper layer, the epilimnion for a long period of time [fr

  10. Microfiltration of radioactive contaminants

    Energy Technology Data Exchange (ETDEWEB)

    Buckley, L P; Slade, J A; Vijayan, S; Wong, C F

    1993-04-01

    Cross-flow microfiltration processing of radioactive liquids has been in use at Chalk River Laboratories for about four years. The separation process removes suspended particles from radioactive waste solutions. The clean liquid can then be treated with conventional reverse osmosis membranes to achieve volume reduction factors approaching 100. Microfiltration removes particles below the rating of 0.2 microns, in part from particle agglomeration. Operating experience relating to a 15 USGPM unit is presented. Coupling microfiltration technology with chemical treatment enhances the removal of soluble species. Research and development experience with the removal of soluble contaminants found in ground water and waste water will be discussed. The technology has advantages over other membrane technologies, namely lower energy costs, a lesser degree of fouling, and a higher recovery of processed solution. Future applications of the technology are addressed. (author). 10 refs., 3 tabs., 4 figs.

  11. Microfiltration of radioactive contaminants

    International Nuclear Information System (INIS)

    Buckley, L.P.; Slade, J.A.; Vijayan, S.; Wong, C.F.

    1993-04-01

    Cross-flow microfiltration processing of radioactive liquids has been in use at Chalk River Laboratories for about four years. The separation process removes suspended particles from radioactive waste solutions. The clean liquid can then be treated with conventional reverse osmosis membranes to achieve volume reduction factors approaching 100. Microfiltration removes particles below the rating of 0.2 microns, in part from particle agglomeration. Operating experience relating to a 15 USGPM unit is presented. Coupling microfiltration technology with chemical treatment enhances the removal of soluble species. Research and development experience with the removal of soluble contaminants found in ground water and waste water will be discussed. The technology has advantages over other membrane technologies, namely lower energy costs, a lesser degree of fouling, and a higher recovery of processed solution. Future applications of the technology are addressed. (author). 10 refs., 3 tabs., 4 figs

  12. Environmental radioactive contamination

    International Nuclear Information System (INIS)

    Saucedo, Edgardo

    2000-01-01

    The environmental radioactive contamination with the scientific and technological advances can produce big benefits or damages to the human beings or the environment. The approval of national or international laws in the population's education so that it can face the topic critically and the scientific formation of human resources and ethically for application of the ionizing radiations, they are the best road to take advantage to the maximum of benefits of these radiations, reducing to the minimum the risks on the man and the environment

  13. Method for electrolytic decontamination of radioactive contaminated metals

    International Nuclear Information System (INIS)

    Tanaka, Akio; Horita, Masami; Onuma, Tsutomu; Kato, Koji

    1991-01-01

    The invention relates to an electrolytic decontamination method for radioactive contaminated metals. The contaminated sections are eluted by electrolysis after the surface of a piece of equipment used with radioactive substances has been immersed in an electrolyte. Metal contaminated by radioactive substances acts as the anode

  14. The development of the American national standard, ''control of radioactive surface contamination on materials, equipment and facilities to be released for uncontrolled use''

    International Nuclear Information System (INIS)

    Shapiro, J.

    1980-01-01

    The American National Standard, Control of Radioactive Surface Contamination on Materials, Equipment and Facilities to be Released for Uncontrolled Use, was developed under the procedures of ANSI for ANSI Main Committee N13 (Radiation Protection) by a working group of the Health Physics Society Standards Committee. This standard provides criteria for the control of materials, equipment and facilities contaminated with radioactivity proposed to be released for uncontrolled use. Permissible contamination limits are specified as well as methods assessing the levels of contamination. This paper reviews the proceedings of the Subcommittee on Radioactive Surface Contamination, the comments received by reviewers of the standard, the resolution of the committee, and the bases for reaching the final limits, recommendations, and measurement procedures. (H.K.)

  15. Decontaminating method for radioactive contaminant

    International Nuclear Information System (INIS)

    Suzuki, Ken-ichi.

    1994-01-01

    After decontamination of radioactive contaminates with d-limonene, a radioactive material separating agent not compatible with liquid wastes caused by decontamination is added to the liquid wastes. Then after stirring, they are stood still to be separated into two phases, and the radioactive materials in the liquid waste phase caused by decontamination are transferred to the phase of the radioactive material separating agent. With such procedures, they can satisfactorily be separated into two phases of d-limonene and the radioactive material separating agent. Further, d-limonene remaining after the separation can be used again as a decontaminating agent for radioactive contaminates. Therefore, the amount of d-limonene to be used can be reduced, to lower the cost for cleaning, thereby enabling to reduce the amount of radioactive wastes formed. (T.M.)

  16. Radioactive contamination in imported foods

    International Nuclear Information System (INIS)

    Kan, Kimiko; Maki, Toshio; Nagayama, Toshihiro; Hashimoto, Hideki; Kawai, Yuka; Kobayashi, Maki; Shioda, Hiroko; Nishima, Taichiro

    1990-01-01

    On April 26, 1986, explosion occurred in Chernobyl nuclear power station in USSR, and radioactivity contamination was brought about in almost all countries in the world. In European countries, crops were contaminated directly with radioactive fallout to high concentration. Also in Japan, after one week the radioactivity higher than usual was detected in environment, and also in vegetables, milk, tea leaves and others. Thereafter, in order to cope with the import of contaminated foods, inspection and watch system was strengthened by deciding the interim limit of radioactive concentration. However the cases of exceeding the interim limit were often reported. In order to remove the harmful foods due to radioactive contamination and to meet the fear of consumers, the authors measured the radioactive concentration in foods distributed in Tokyo and investigated the actual state of contamination. The samples were 920 imported foods. The experimental method, the preparation of samples, the method of analysis and the results are reported. The samples in which the radioactive concentration exceeding 50 Bq/kg was detected were 25 cases. The food having the high frequency of detection was flavors. (K.I.)

  17. Technologies for remediation of radioactively contaminated sites

    International Nuclear Information System (INIS)

    1999-06-01

    This report presents particulars on environmental restoration technologies (control and treatment) which can be applied to land based, radioactively contaminated sites. The media considered include soils, groundwater, surface water, sediments, air, and terrestrial and aquatic vegetation. The technologies addressed in this report can be categorized as follows: self-attenuation (natural restoration); in-situ treatment; removal of contamination; ex-situ treatment; and transportation and final disposal. The report provides also background information about and a general approach to remediation of radioactively contaminated sites as well as some guidance for the selection of a preferred remediation technology. Examples of remediation experience in Australia and Canada are given it annexes

  18. Technologies for remediation of radioactively contaminated sites

    Energy Technology Data Exchange (ETDEWEB)

    1999-06-01

    This report presents particulars on environmental restoration technologies (control and treatment) which can be applied to land based, radioactively contaminated sites. The media considered include soils, groundwater, surface water, sediments, air, and terrestrial and aquatic vegetation. The technologies addressed in this report can be categorized as follows: self-attenuation (natural restoration); in-situ treatment; removal of contamination; ex-situ treatment; and transportation and final disposal. The report provides also background information about and a general approach to remediation of radioactively contaminated sites as well as some guidance for the selection of a preferred remediation technology. Examples of remediation experience in Australia and Canada are given it annexes Refs, figs, tabs

  19. Radioactive contamination of environment

    International Nuclear Information System (INIS)

    Chytil, I.

    1981-01-01

    A computer model is discussed describing radioactivity transport between the source and the organism. The model is to be applied in assessing the effect of a nuclear installation on the organism. Fortran and Pascal appear to be the most appropriate computer languages. With respect to internal memory requirements, the program file is estimated to consist of a control program and a number of subprograms. Upon setting the radioactivity transport and the output requirements the control program should recall the necessary subprograms. The program file should allow the complete data file and the solutions of all possible radioactivity transport variants to be inputted. It is envisaged that several subprograms will be available for one type of radioactivity transport, this depending on different accuracy of the transport description. Thus, the requirements for input data will also differ. (Z.M.)

  20. Foodstuffs (radioactive contamination)

    International Nuclear Information System (INIS)

    Thompson, Donald; Taylor, Teddy; Campbell-Savours, D.N.

    1987-01-01

    The proceedings are given of the debate in the UK House of Commons on the maximum permitted radioactivity levels for foodstuffs, feeding stuffs and drinking water in the case of abnormal levels of radioactivity or of a nuclear accident. The motion takes note of European Community Document no. 7183/87 and urges the Community to assure a common standard of health protection by adopting a rational set of scientifically based intervention levels for foodstuffs. (UK)

  1. Strippable core-shell polymer emulsion for decontamination of radioactive surface contamination

    International Nuclear Information System (INIS)

    Hwang, Ho-Sang; Seo, Bum-Kyoung; Lee, Kune-Woo

    2011-01-01

    In this study, the core-shell composite polymer for decontamination from the surface contamination was synthesized by the method of emulsion polymerization and blends of polymers. The strippable polymer emulsion is composed of the poly(styrene-ethyl acrylate) [poly(St-EA)] composite polymer, poly(vinyl alcohol) (PVA) and polyvinylpyrrolidone (PVP). The morphology of the poly(St-EA) composite emulsion particle was core-shell structure, with polystyrene (PS) as the core and poly(ethyl acrylate) (PEA) as the shell. Core-shell polymers of styrene (St)/ethyl acrylate (EA) pair were prepared by sequential emulsion polymerization in the presence of sodium dodecyl sulfate (SDS) as an emulsifier using ammonium persulfate (APS) as an initiator. Related tests and analysis confirmed the success in synthesis of composite polymer. The products are characterized by FT-IR spectroscopy, TGA that were used, respectively, to show the structure, the thermal stability of the prepared polymer. Two-phase particles with a core-shell structure were obtained in experiments where the estimated glass transition temperature and the morphologies of emulsion particles. Decontamination factors of the strippable polymeric emulsion were evaluated with the polymer blend contents. (author)

  2. Non-radioactive stand-in for radioactive contamination. I. Non-radioactive tests

    International Nuclear Information System (INIS)

    Rohe, M.J.; Rankin, W.N.; Postles, R.L.

    1985-01-01

    Candidate non-radioactive materials for use as a stand-in for radioactive contamination during application of a high-pressure, hot water decontamination were identified and evaluated. A stand-in for radioactive contamination is needed to evaluate the decontaminability of replacement canyon cranes at the manufacturers location where actual radioactive contamination cannot be used. This evaluation was conducted using high-pressure, hot-water at 420 psi, 190 0 F, and 20 gal/min through a 1/8-in.-diam nozzle, the decontamination technique preferred by SRP Separations Department for this application. A non-radioactive stand-in for radioactive contamination was desired that would be removed by direct blast stream contact but would remain intact on surfaces where direct contact does not occur. This memorandum describes identification of candidate non-radioactive stand-in materials and evaluation of these materials in screening tests and tests with high-pressure, hot-water blasting. The following non-radioactive materials were tested: carpenter's line chalk; typing correction fluid; dye penetrant developer; latex paint with attapulyite added; unaltered latex paint; gold enamel; layout fluid; and black enamel. Results show that blue layout fluid and gold enamel have similar adherence that is within the range expected for actual radioactive contamination. White latex paint has less adherence than expected for actual radioactive contamination. The film was removed at a rate of 2 . Black enamel has more adherence than expected from actual radioactive contamination. In these tests ASTM No. 2B surfaces were harder to clean than either ASTM No. 1 or electropolished surfaces which had similar cleaning properties. A 90 0 blast angle was more effective than a 45 0 blast angle. In these tests there was no discernible effect of blast distance between 1 and 3 ft

  3. Radioactive contamination of recycled metals

    International Nuclear Information System (INIS)

    Lubenau, J.O.; Cool, D.A.; Yusko, J.G.

    1996-01-01

    Radioactive sources commingled with metal scrap have become a major problem for the metals recycling industry worldwide. Worldwide there have been 38 confirmed reports of radioactive sources accidentally smelted with recycled metal. In some instances, contaminated metal products were subsequently distributed. The metal mills, their products and byproducts from the metal making process such as slags, crosses and dusts from furnaces can become contaminated. In the U.S., imported ferrous metal products such as reinforcement bars, pipe flanges, table legs and fencing components have been found contaminated with taco. U.S. steel mills have unintentionally smelted radioactive sources on 16 occasions. The resulting cost for decontamination waste disposal and temporary closure of the steel mill is typically USD 10,000,000 and has been as much as USD 23,000,000. Other metal recycling industries that have been affected by this problem include aluminum, copper, zinc, gold, lead and vanadium. (author)

  4. 49 CFR 175.705 - Radioactive contamination.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Radioactive contamination. 175.705 Section 175.705... Regulations Applicable According to Classification of Material § 175.705 Radioactive contamination. (a) A... (radioactive) materials that may have been released from their packagings. (b) When contamination is present or...

  5. Radioactive contamination of sewage sludge

    International Nuclear Information System (INIS)

    Soeder, C.J.; Zanders, E.; Raphael, T.

    1986-01-01

    Because of the radioactivity released through the explosion of the nuclear reactor near Chernobyl radionuclides have been accumulated to a significant extent in sewage sludge in the Federal Republic of Germany. This is demonstrated for samples from four activated sludge plants according to a recent recommendation of the German Commission for Radiation Protection, there is until now no reason to deviate from the common practices of sludge disposal or incineration. The degree of radioactive contamination of plant materials produced on farm lands on which sewage sludge is being spread cannot be estimated with sufficient certainty yet. Additional information is required. (orig.) [de

  6. The development of the American National Standard 'control of radioactive surface contamination on materials equipment and facilities to be released for uncontrolled use'

    International Nuclear Information System (INIS)

    Shapiro, J.

    1980-01-01

    A new standard submitted by the Health Physics Society Standards Committee to the American National Standards Institute concerning radioactive surface contamination of materials and equipment is discussed. The chronological events in the development of this standard are given. The standard provides criteria for the release for uncontrolled use of materials, equipment and facilities contaminated or potentially contaminated with radioactivity. Permissible contamination limits are specified for: 1) long lived alpha emitters except natural uranium and thorium, 2) more hazardous beta-gamma emitters, 3) less hazardous beta-gamma emitters and 4) natural uranium and thorium. A contamination reference level of 1000 dpm/100 cm 2 for 90 Sr was set as the basis for assigning limits to radionuclides presenting an ingestion hazard and other radionuclides were grouped based on the values of their maximum permissible concentration (MPC) in water relative to 90 Sr. The contamination limit for 239 Pu was chosen as the basis for assigning limits based on MPC in air to radionuclides presenting an inhalation hazard; a value of 100 dpm/100 cm 2 was adopted in the standard. An upper limit of 5000 dpm/100 cm 2 for surface contamination was selected for the standard. (UK)

  7. Analysis of surface contributions to external doses in a radioactively contaminated urban environment designed by the EMRAS-2 Urban Areas Working Group

    International Nuclear Information System (INIS)

    Hwang, Won Tae; Jeong, Hae Sun; Jeong, Hyo Joon; Kim, Eun Han; Han, Moon Hee; Kim, In Gyu

    2013-01-01

    Highlights: ► External dose and contribution from radio-activated surface were evaluated for EMRAS-2 Urban Areas Working Group scenarios. ► The external doses showed a distinctive difference with the locations and precipitation. ► The contribution of contaminated surfaces for external dose depends on locations and precipitation. ► These results provide the essential information for decision-making support of countermeasures. - Abstract: The EMRAS-2 Urban Areas Working Group, which is supported by the IAEA, has designed a variety of accidental scenarios to test and improve the capabilities of the models used for an evaluation of radioactive contamination in an urban environment. A variety of models including a Korean model, METRO-K, are used for predictive results on the hypothetical scenarios. This paper describes the predictive results of METRO-K for the hypothetical scenarios designed in the Working Group. The external dose resulting from the air contamination of Co-60 was evaluated, and its contribution was analyzed with time as a function of the location of a receptor and precipitation conditions at the time of the contamination event. As a result, the external doses showed a distinctive difference with the locations to be evaluated and the precipitation conditions. Moreover, the contribution of contaminated surfaces for external doses was strongly dependent on the locations to be evaluated and the precipitation conditions. These results will provide essential information to assist the decision-making of appropriate countermeasures in an emergency situation of a radioactively contaminated urban environment

  8. Radiation exposure to skin following radioactive contamination

    International Nuclear Information System (INIS)

    Baumann, H.; Beyermann, M.; Kraus, W.

    1989-01-01

    In the case of skin contamination intensive decontamination measures should not be carried out until the potential radiation exposure to the basal cell layer of the epidermis was assessed. Dose equivalent rates from alpha-, beta- or photon-emitting contaminants were calculated with reference to the surface activity for different skin regions as a function of radiation energy on the condition that the skin was healthy and uninjured and the penetration of contaminants through the epidermis negligible. The results have been presented in the form of figures and tables. In the assessment of potential skin doses, both radioactive decay and practical experience as to the decrease in the level of surface contamination by natural desquamation of the stratum corneum were taken into account. 9 figs., 5 tabs., 46 refs. (author)

  9. Assessment of the dynamics of the radioactivity contents in surface waters in contaminated areas

    International Nuclear Information System (INIS)

    Komissarov, F.D.; Datskevich, P.I.; Golikov, Y.N.; Basharina, L.P.; Churack, T.N.; Khvaley, O.D.

    1997-01-01

    In the connection with Chernobyl APS accident, since 1988 a network of sites was established for radioecological monitoring of surface water systems, mainly, small rivers on all Belarus territory. Small rivers are the principal way of radionuclides run off in liquid and solid discharges during rains and high-floods and their re-distribution in landscapes. The components of water systems radio-monitoring were water and water suspensions, area water-collection, bottom deposits and biota. In the paper the data are cited of radioecological studies of water systems components. Their analysis is done and some conclusions made which may be used for the development of radioecological prognosis and for taking environmental measures

  10. Comparative evaluations of surface contamination detectors calibration with radioactive sources - used in the Goiania accident, and standard sources

    International Nuclear Information System (INIS)

    Becker, P.H.B.; Marecha, M.H.H.

    1997-01-01

    The construction of Cs-137 standard flat sources for calibration of surface contamination detectors, used in the Goiania accident in 1987, is described and the procedures adopted are reported. At that time, standard sources were not available. Nowadays the Instituto de Radioprotecao e Dosimetria has standard sources acquired from Amersham which are used as calibration standards for surface contamination detectors. Comparative evaluations between the standard flat sources constructed for the accident and the calibrated ones are presented

  11. Some bioindicators of radioactive contamination

    International Nuclear Information System (INIS)

    Cosma, C.; Cozmuta, I.; Micu, C.

    1996-01-01

    The lessons that could be learned from the Chernobyl accident were numerous and encompassed all areas. One of those lead to the discovery of new monitoring methods which also supply to cost-effective solutions to control contaminant radioactive discharges in the environment. Through the measurements performed, we discovered that some samples, because of their radioactive content restrained also for long periods of time, can be used as bioindicators. Hen eggs between May 1-30 1986 were analysed (identification of radionuclides with a Ge(Li) detector and measuring of total gamma activity with NaI(T1)). Various aspects pursued revealed that eggs are precious witness of vegetable food contamination with fission products, especially Ba-140 and I-131, behaving as radionuclide separators (Ba-140 in egg shell -301 Bq/egg and I-131 in the content - 182 Bq/egg). Some of the most important pharmaceutical plants from Transylvania measured during 1986-1994 period presents high cesium radioactivity. The perennial plants (as Lichen Islandicus) for the same period accumulated a greater activity that the annual ones. Especially the lichen, because of the their slow decreasing activity are suitable as biological detectors also in retrospective measurements. Measuring the activity of some pollen samples was rediscovered. The pollen grains, during their transport in air by the bees, are acting like a filter for radionuclides so that we could use they to monitor the deliverance of these substances in air. (author)

  12. Radioactive contamination of the Guatemalan marine environment

    International Nuclear Information System (INIS)

    Perez-Sabino, J.F.; Oliva de Sandoval, B.E.; Orozco-Chilel, R.M.; Aguilar-Sandoval, E.

    1999-01-01

    As part of the IAEA TC project GUA/2/005 'Radioactivity and Contamination of the Marine Environment in Guatemala', concentrations of artificial and natural radionuclides have been determined in marine water and sediments, giving important information to establish the base line of the natural radioactivity and the radioactive contamination in this area that not have been studying

  13. Radioactive contamination of the Guatemalan marine environment

    Energy Technology Data Exchange (ETDEWEB)

    Perez-Sabino, J F; Oliva de Sandoval, B E; Orozco-Chilel, R M; Aguilar-Sandoval, E [Universidad de San Carlos de Guatemala, Facultad de Ciencias Quimicas y Farmacia, Unidad de Analisis Instrumental, Guatemala C.A. (Guatemala)

    1999-07-01

    As part of the IAEA TC project GUA/2/005 `Radioactivity and Contamination of the Marine Environment in Guatemala`, concentrations of artificial and natural radionuclides have been determined in marine water and sediments, giving important information to establish the base line of the natural radioactivity and the radioactive contamination in this area that not have been studying 4 refs, 1 fig., 4 tabs

  14. Decontamination method for radioactively contaminated material

    International Nuclear Information System (INIS)

    Shoji, Yuichi; Mizuguchi, Hiroshi; Sakai, Hitoshi; Komatsubara, Masaru

    1998-01-01

    Radioactively contaminated materials having surfaces contaminated by radioactive materials are dissolved in molten salts by the effect of chlorine gas. The molten salts are brought into contact with a low melting point metal to reduce only radioactive materials by substitution reaction and recover them into the low melting point metal. Then, a low melting point metal phase and a molten salt phase are separated. The low melting point metal phase is evaporated to separate the radioactive materials from molten metals. On the other hand, other metal ions dissolved in the molten salts are reduced into metals by electrolysis at an anode and separated from the molten salts and served for regeneration. The low melting point metals are reutilized together with contaminated lead, after subjected to decontamination, generated from facilities such as nuclear power plant or lead for disposal. Since almost all materials including the molten salts and the molten metals can be enclosed, the amount of wastes can be reduced. In addition, radiation exposure of operators who handle them can be reduced. (T.M.)

  15. Contamination due to radioactive materials

    International Nuclear Information System (INIS)

    Woodhead, D.S.

    1984-01-01

    The peaceful exploitation of radioactivity and the expansion of the nuclear power programme ensure that the disposal of radioactive wastes will cause contamination of the marine environment in the foreseeable future. The exposure of marine organisms to radioactivity from wastes has been studied in depth and related to exposure to natural background radiation. Concentrations of natural radionuclides and those from marine waste disposal have been measured at various stations in the oceans and seas around the world. The fate of radionuclides at four representative sites has been studied and the concentrations of radionuclides in oysters, porphyra, plaice in the Windscale discharge area have been measured. The extent of human exposure, particularly with reference to seafood consumption in local fishing communities, has been assessed. Effects of radiation on developing fish embryos and eggs and genetic radiation effects in aquatic organisms has been studied. The above studies reveal that the controls applied to the discharge of radioactive wastes to limit hazards to humans also provide adequate protection for populations of marine organisms. (U.K.)

  16. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1

    International Nuclear Information System (INIS)

    Lambert, K.A.; Mitchell, M.M.; Jean, D.; Brown, C.; Byrd, C.S.

    1997-09-01

    This report describes the survey and removal of radioactive surface contamination at Sandia's Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope

  17. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, K.A.; Mitchell, M.M. [Brown and Root Environmental, Albuquerque, NM (United States); Jean, D. [MDM/Lamb, Inc., Albuquerque, NM (United States); Brown, C. [Environmental Dimensions, Inc., Albuquerque, NM 87109 (United States); Byrd, C.S. [Sandia National Labs., Albuquerque, NM (United States)

    1997-09-01

    This report describes the survey and removal of radioactive surface contamination at Sandia`s Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope.

  18. Radioactive food and environment contamination

    International Nuclear Information System (INIS)

    Yousif, A.M.

    2001-01-01

    The Food and Environment Control Centre of Abu Dhabi Municipality with the help of IAEA has established facilities for regular monitoring of food and environmental samples for radioactive contamination. The Centre is now capable of measuring gamma, beta as well as alpha activity in different types of samples. The main activities in the area of food monitoring are as follows: General monitoring of food gamma radionuclides in foodstuffs by high resolution gamma spectrometry; Determination of specific gamma radionuclides in foodstuffs by high resolution gamma spectrometry; Radiochemical determination of Sr-90 using liquid scintillation analyzer or by gas flow proportional counter; Measurement of gross alpha activity in drinking water

  19. Biological cycles of radioactive contaminants

    International Nuclear Information System (INIS)

    Michon, M.-G.

    1959-01-01

    Artificial radio-elements (synthesized for scientific or industrial purposes)having been released, may be absorbed by plants or animals, and may eventually involve a catenation of organisms as some feed on the others. All organisms living in a polluted river become more radioactive than the water, which was to be expected, in as much as organisms are hypertonic in respect to sweet water. Conversely, soil brings into play physico-chemical phenomena (absorption) such that plants can get only a small portion of contaminating radio-elements, land animal feeding on such plants are relatively less exposed to contamination, and carnivorous animals feeding on herbivorous are still less exposed. Man, notably is fairly well protected, whereas lower organisms, notably unicellular organisms may suffer (mutations..). Reprint of a paper published in 'Revue de Pathologie Generale et de Physiologie Clinique', n. 707, April 1959, p. 505-514 [fr

  20. Examination of a measuring method for fallout radioactivity released by the accident of the Fukushima Dai-ichi NPS. Surface contamination measurement

    International Nuclear Information System (INIS)

    Yoshii, Taiki; Kawasaki, Satoru

    2013-08-01

    Radioactive nuclides were released in the atmosphere by the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station in March, 2011, and they are detected on the materials that had no artificial radioactive nuclides before the accident. Confronted with this situation, NISA issued a guideline titled 'A guideline regarding treatment of materials in nuclear facilities considering the influence of fallout released from the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station' on March 30, 2012. Nuclear Regulatory Authority refers to applying the existing bylaw until the time to make decision of the updated bylaw. The guideline shows that after judging whether there is the influence of fallout or not, the conventional clearance and NR systems can be used when there is no influence of fallout. On the other hand, the special treatment is required when it is judged that there is the influence. This report describes a specific example of measuring method to evaluate the influence of fallout, in case of surface contamination. This report focused surface contamination of flat object as target. Preliminary investigation shows that the distribution of surface contamination due to fallout is near to lognormal distribution. Therefore, the sampling measurement can be adopted. The average surface contamination of target is decided from sampling data by using 90% upper confidence limit of Chebyshev inequality. Also, the minimum sampling number is decided. The evaluation of the influence of fallout is judged from the result of surface contamination measurement, weight of target and surface area of target. (author)

  1. Contamination of foods by radioactive rains

    Energy Technology Data Exchange (ETDEWEB)

    Obo, F; Wakamatsu, C; Nakae, Y; Higasayama, S

    1955-01-01

    The radioactivities of various vegetable foods contaminated by radioactive rains in May, 1954, in the Kagoshima Area were detected. Tea showed especially high radioactivities which could be extracted with hot water. Radioactive Nb, Zr, Hf, Ce, Y, Pr, and La were detected in the hot water extractions of tea by ion-exchange chromatography. The partial contribution of /sup 40/K in these radioactive vegetables was critically examined.

  2. Decontamination of radioactively contaminated surfaces - Method for testing and assessing the ease of decontamination (International Standard Publication ISO 8690:1988)

    International Nuclear Information System (INIS)

    Stefanik, J.

    2001-01-01

    The specifications laid down in this International Standard apply to the testing of surfaces which may become contaminated by radioactive materials. Decontaminability data obtained using this test method are not applicable to technical systems where layers of contaminating materials are formed as a result of long-term application of higher temperatures and pressures (for example primary circuits of nuclear reactors). The purpose of the test is to assess the ease of decontamination of surfaces under laboratory conditions. In practical applications, it may be important to consider other qualities, such as chemical, mechanical and radiation resistance and long-term stability in the selection of the materials to be used. It should be recognized that further decontamination tests under simulated service conditions may be needed

  3. Measurement of radioactivity in contaminated crops

    Energy Technology Data Exchange (ETDEWEB)

    Yamada, Y; Hasegawa, M; Kihara, T

    1956-01-01

    A method called the Direct Method was developed to correct for natural /sup 40/K radiation in plant samples. The K content of the ashed sample is determined by flamephotometry. The radioactivity in a 100 mg sample is measured and the natural radioactivity from /sup 40/K determined by calculation subtracted. Tea samples tested gave evidence of contamination by radioactive fallout.

  4. Status of outdoor radioactive contamination at the Hanford Site

    International Nuclear Information System (INIS)

    McKinney, S.M.; Markes, B.M.

    1994-12-01

    This document summarizes the status of outdoor radioactive contamination near Hanford Site facilities and disposal sites. It defines the nature and areal extend of the radioactively contaminated areas and describes the historical, ongoing, and planned radiological monitoring and control activities. Radioactive waste has been disposed of to the soil column since shortly after the reactors and production facilities began operating. Radioactive liquid wastes were placed directly into the ground via liquid discharges to cribs, ponds, ditches, and reverse wells. Solid wastes were placed in trenches, burial vaults, and caissons. Although the Hanford Site covers 1,450 km 2 , the radioactively contaminated area is only about 36 km 2 or 2.5% of the original site. Over time, contamination has migrated from some of the waste management sites through various vectors (e.g., burrowing animals, deep-rooted vegetation, erosion, containment system failure) or has been deposited to the surface soil via spills and unplanned releases (e.g., line leaks/breaks, tank leaks, and stack discharges) and created areas of outdoor radioactivity both on and below the surface. Currently 26 km 2 are posted as surface contamination and 10 km 2 are posted as underground contamination

  5. Remediation of sites with dispersed radioactive contamination

    International Nuclear Information System (INIS)

    2004-01-01

    disciplines, including the health sciences, chemistry, physics, geology, microbiology and environmental engineering, is necessary in order to develop technical solutions. It is also necessary to include information on the political, social and economic context. This report describes remediation techniques that are applicable to dispersed radioactive contamination at a variety of sites, including surface soil, the vadose zone, surface water, sediments and groundwater

  6. Evaluation of Unfixed Tritium Surface Contamination

    International Nuclear Information System (INIS)

    Postolache, C.; Matei, Lidia

    2005-01-01

    Surface unfixed radioactive contamination represents the amount of surface total radioactive contamination which can be eliminated by pure mechanical processes. This unfixed contamination represents the main risk factor for contamination of the personnel which operates in tritium laboratories. Unfixed contamination was determined using sampling smears type FPCSN-PSE-AA. Those FPCSN-PSE-AA smears are disks of expanded polystyrene which contain acrylic acid fragments superficially grafted. Sampling factor was determinated by contaminated surface wiping with moisten smears in 50 μL butylic alcohol and activity measuring at liquid scintillation measuring device. Sampling factor was determined by the ratio between measured activity and initially real conventional activity. The sampling factor was determined for Tritium Laboratory existent surfaces: stainless steel, aluminum, glass, ceramics, linoleum, washable coats, epoxy resins type ALOREX LP-52.The sampling factors and the reproducibility were determined in function of surface nature

  7. Control of the surface radioactive contamination in the field of biological research; Control de la contaminacion radiactiva superficial en el ambito de la investigacion biologica

    Energy Technology Data Exchange (ETDEWEB)

    Calvo, S.; Encina, A. de la; Gaspar, J.; Macias, M. T.; Sanchez, A.; Usera, F.

    2012-11-01

    The manipulation of unsealed sources in biomedical research involves significant risk of radioactive contamination. the aim of this study has been to analyze the radioactive contamination occurring in the field of biomedical research, assessing its magnitude, identifying the equipment that can be contaminated with higher probability and monitoring the evolution of the contaminations production taking into account the radioisotopes and the activities uses, and the radiation protection control applied. The data used for this study correspond to a very lengthy period of time and it have been collected in the radioactive facility, of the Centro Nacional de Biotecnologia (CSIC), a very large biological research centre that can be used perfectly as a reference for this area. The results obtained show a gradual and significant decrease in the incidence of the radioactive contamination. This is due to the optimization of radiation protection standards applied and the implementation or a systematic operational radiation protection program. (Author) 13 refs.

  8. Method of preventing contaminations in radioactive material handling facilities

    International Nuclear Information System (INIS)

    Inoue, Shunji.

    1986-01-01

    Purpose: To prevent the contamination on the floor surface of working places by laying polyvinyl butyral sheets over the floor surface, replacing when the sheets are contaminated, followed by burning. Method: Polyvinyl butyral sheets comprising 50 - 70 mol% of butyral component are laid in a radioactive material handling facility, radioactive materials are handled on the polyvinyl butyral sheets and the sheets are replaced when contaminated. The polyvinyl butyral sheets used contain 62 - 68 mol% of butyral component and has 0.03 - 0.2 mm thickness. The contaminated sheets are subjected to burning processing. This can surely collect radioactive materials and the sheets have favorable burnability, releasing no corrosive or deleterious gases. In addition, they are inexpensive and give no hindrance to the workers walking. (Takahashi, M.)

  9. Process for reducing radioactive contamination in phosphogypsum

    International Nuclear Information System (INIS)

    Palmer, J.W.; Gaynor, J.C.

    1983-01-01

    In a process for reducing radioactive contamination of phosphogypsum, anhydrite crystals are obtained through dehydration of the phosphogypsum in strong sulfuric acid: a portion of the anhydrite crystals is converted to subtantially radiation free gypsum by crystallizing out on radiation free gypsum seed crystals. These coarse radiation free gypsum crystals are then separated from the small anhydrite crystal relics containing substantially all of the radioactive contamination

  10. Cleanup of radioactivity contamination in environment

    International Nuclear Information System (INIS)

    Kosako, Toshiso

    1994-01-01

    Environmental radioactivity cleanup is needed under a large scale accident in a reactor or in an RI irradiation facility which associates big disperse of radioactivities. Here, the fundamental concept including a radiation protection target, a period classification, planning, an information data base, etc. Then, the methods and measuring instruments on radioactivity contamination and the cleanup procedure are explained. Finally, the real site examples of accidental cleanup are presented for a future discussion. (author)

  11. Surface contamination technology in decommissioning of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Ishiguro, Hideharu

    2012-01-01

    Surface contamination measurement is the most basic technology in radiation control of the nuclear and radiation facilities. Loose surface contamination causes internal exposure through airborne contamination. Surface contamination measurement is recently more important in the waste management such as confirmation of decontamination factor, contamination survey of carried-out materials from radioactive control area, and application of clearance level. This report describes the base of surface contamination standards, meaning of contamination in decommissioning, relationship between clearance level and surface contamination, and current technology of surface contamination measurement. (author)

  12. Bonding of radioactive contamination. III. Auger electron spectroscopic investigation

    International Nuclear Information System (INIS)

    Rankin, W.N.; Whitkop, P.G.

    1983-01-01

    The mechanisms by which radioactive contamination would be bonded to a DWPF canister surface are being investigated. Tests with low pressure water and air-injected water decontamination of radioactive specimens showed that bonding of contamination increases rapidly with postoxidation temperature. Even with the least severe temperature conditions expected on the waste glass canister, bonding is so great that decontamination cannot be affected by water-only techniques. A preoxidation film increased rather than decreased bonding. This memorandum describes detailed surface analyses of coupons simulating DWPF canister surfaces. Based on this examination we conclude: contamination will be dispersed throughout the oxide film on DWPF canisters. Contamination is concentrated at the surface, decreasing farther into the oxide film; some samples contain sludge contamination at the steel/oxide interface. This was not the case for semi-volatile (Cs 2 O) contamination; in samples with contamination at the steel/oxide interface, at least 80% of the contamination is usually in the oxide layer; no difference in contamination dispersion between preoxidized and non-preoxidized samples was found; and postoxidation atmosphere had no effect on the contamination dispersion within the oxide layer. 6 references, 9 figures

  13. Method of electrolytic decontamination of contaminated metal materials for radioactivity

    International Nuclear Information System (INIS)

    Harada, Yoshio; Ishibashi, Masaru; Matsumoto, Hiroyo.

    1985-01-01

    Purpose: To electrolytically eliminate radioactive materials from metal materials contaminated with radioactive materials, as well as efficiently remove metal ions leached out in an electrolyte. Method: In the case of anodic dissolution of metal materials contaminated with radioactivity in an electrolyte to eliminate radioactive contaminating materials on the surface of the metal materials, a portion of an electrolytic cell is defined with partition membranes capable of permeating metal ions therethrough. A cathode connected to a different power source is disposed to the inside of the partition membranes and fine particle of metals are suspended and floated in the electrolyte. By supplying an electric current between an insoluble anode disposed outside of the partition membranes and the cathode, metal ions permeating from the outside of the partition membranes are deposited on the fine metal particles. Accordingly, since metal ions in the electrolyte are removed, the electrolyte can always be kept clean. (Yoshihara, H.)

  14. Radioactive contamination in imported foods (II)

    International Nuclear Information System (INIS)

    Kan, Kimiko; Maki, Toshio; Hashimoto, Hideki; Kawai, Yuka; Nagayama, Toshihiro; Kobayashi, Maki; Shioda, Hiroko; Nishima, Taichiro

    1991-01-01

    Five years have elapsed since the Chernobyl accident, but the effect of radioactivity contamination to foods has continued. Also in Japan, the imported foods which were ordered by the Ministry of Health and Welfare to be sent back due to radioactivity contamination do not cease. In fiscal year 1990, three cases occurred: tea from Albania, mushrooms from Yugoslavia and spices from france. If those are not checked at quarantines, it is feared that such foods are distributed in Japan. Among the foods which were ordered to be sent back in the past, there were those from Brazil and Hong Kong where the effect of the Chernobyl accident is little, and the foods contaminated with radioactivity spread worldwide through import and export. Therefore, attention must be paid to the foods from the countries where radioactivity contamination is little. Also it is feared that Japanese foods may be contaminated by being cultivated with imported feed, soil and fertilizer, for which there is no regulation. In this report, the radioactivity contamination of imported foods in fiscal year 1990 is described, and the experimental method and the results are reported. (K.I.)

  15. Survey of radioactive contamination for foodstuffs

    International Nuclear Information System (INIS)

    Lee, Wan No; Lee, Chang Wu; Choi, Geun Sik; Cho, Yeong Hyeon; Kang, Mun Ja; Cheong, Geun Ho; Kim, Hui Ryeong; Park, Du Won; Park, Hyo Guk; Kwak, Ji Yeon

    2006-11-01

    After the Chernobyl nuclear accident in 1986, a lot of countries including EU, Japan, USA are to strengthen survey of radioactive contamination for foodstuffs. Our country has also surveyed radioactive contamination of the imported foodstuffs and started to check continuously the radioactivity contamination of the open market foodstuffs since 2003. In this year, imported foodstuffs(130 samples) and domestic foodstuffs(10 samples) are analyzed to investigate the radioactive contamination. Sampled foodstuffs items are collected from the open markets; one group is the imported foodstuffs and the other group is the domestic foodstuffs producted around nuclear facilities and northeast of Sokcho city concerning recent situations. Samples are usually bought from traditional markets, mart, department store or the Internet. After pretreatments such as drying, ashing, and homogenization, all samples were analyzed by gamma spectrometer system for survey and assessment of radioactive contamination. The 131 I radionuclide isn't detected among all foodstuffs(imported and domestic). The 137 Cs radionuclide among the regulation radionuclides( 137 Cs, 13 4 C s, 131 I) of food code is only detected at the imported foodstuffs but its level is far below the maximum permitted level. For the improvement of measurement confidence, the developed analysis method is tested by the participation of the national and international intercomparison. The developed method based on test results and international standard would be used at radioactive analysis as well as an education of relative workers. It could be applied as the basis data for amending the analysis method of food code. It is technically supported for radioactive analysis of commercial company and the government including KFDA. Finally these results would be used to solve an ambiguous anxiety of a people for radiation exposure by foodstuffs intake and help the KFDA to manage systematically the radioactive contamination and to give

  16. Substantiation of the permissible radioactive contamination of working clothes

    International Nuclear Information System (INIS)

    Shcherbakov, V.L.; Korostin, A.S.

    1977-01-01

    A permissible level of working clothes contamination was determined on the base of the main migration routes of radioactive contaminants: permeation directly through the clothes into subclothes space on skin surface, emission into the air with amount of contaminants subsequently got by the organism of a working person through inhalation as well as transfer in the process of contacting of contaminated working clothes and surfaces of premises equipment, working person hands with amount of contaminants posteriorly got by the organism by alimentary or inhalation ways. Using the experimental and literature data available the permissible levels of working clothes contamination for the mentioned migration routes of radioactive materials have been calculated. According to the data obtained the permissible levels of working clothes contamination must not exceed 4 alpha-part/(cm 2 xmin) for contamination with high-tonic isotopes, 20 alpha-part./(cm 2 xmin) with other alpha-detine isotopes, 1000 beta-part./(cm 2 xmin) with beta-active ones. The permissible level of contamination of additional materials of the individual protection in the case of their contamination with high-tonic alpha-actine isotopes must not exceed 50 alpha-part./(cm 2 xmin), 200 alpha-part./(cm 2 xmin) for contamination th other alpha-active isotopes and 400 beta-part./(cm 2 xmin) with beta-active isotopes

  17. ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS

    International Nuclear Information System (INIS)

    R.H. Little, P.R. Maul, J.S.S. Penfoldag

    2003-01-01

    This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible

  18. Transboundary Movement of Radioactively Contaminated Scrap Metal - Lessons Learned

    Energy Technology Data Exchange (ETDEWEB)

    Nizamska, M., E-mail: m.nimzamska@bnra.bg [Emergency Planning and Preparedness Division, Bulgarian Nuclear Regulatory Agency, Sofia (Bulgaria)

    2011-07-15

    Starting in 1989, Bulgaria has undergone a comprehensive transformation of its economy and social conditions. Part of this process is related to the intensive privatization that started in 2001. This privatization included facilities, as well as sites that use radioactive material for different applications - industry, medicine, agriculture, science, etc. The rapid change of property ownership and, in some cases, the resulting bankruptcy, has caused difficulties in tracing and identifying radioactive sources and materials and a deterioration of the system of safety, physical protection, etc. of radioactive material. In some cases, radioactive sources were stolen because of the value of their protective containers and sold for scrap metal. This led to the occurrence of different types of radiation incidents, mainly related to the discovery of radioactive sources in scrap metal. The consequences of these incidents include the risk of radiation exposure of the workers at scrap metal yards or reprocessing facilities and of members of the public and, in addition, radioactive contamination of the environment. The Bulgarian Nuclear Regulatory Agency (BNRA) has been responding to these incidents and has carried out a series of measures to improve the control over materials (e.g. activated or surface contaminated materials) and radioactive sources and to strengthen the preventive, monitoring, emergency preparedness and mitigating measures at facility, national and transboundary levels. This paper presents an analysis of the lessons learned by the BNRA and of the control of the transboundary movement of radioactively contaminated scrap metal through the territory of Bulgaria. (author)

  19. Rehabilitation of radioactive contaminated forests

    International Nuclear Information System (INIS)

    Panfilov, A.V.; Uspenskaya, E.Ju.

    2002-01-01

    As a result of radiation accidents and nuclear-weapon tests at the territory of the former USSR a part of the Forest Fund of 23 subjects of the Russian Federation has been contaminated by radionuclides. The contaminated forests, which are included in a structure of more than 130 forest management units (leskhozes) and more then 330 local forest management units, as a rule, are located in highly inhabited regions with traditionally intensive forestry management and high level of forest resources use. To provide radiologically safe forest management in the contaminated areas, the Federal Forest Service has developed and validated a special system of countermeasures. Use of this system makes it possible to diminish significantly the dose to personnel, to exclude the use of forest products with contamination exceeding radiological standards and to provide protection of the forest as a biogeochemical barrier to radionuclide migration from contaminated areas to human habitat. (author)

  20. Technologies for remediating radioactively contaminated land

    International Nuclear Information System (INIS)

    Pearl, M.

    2000-01-01

    This paper gives an overview of technologies that can be used for the remediation of radioactively contaminated ground. There are a wide variety of techniques available -most have established track records for contaminated ground, though in general many are only just being adapted to use for radioactively contaminated ground. 1) Remediation techniques for radioactively contaminated ground involve either removal of the contamination and transfer to a controlled/contained facility such as the national LLW repository at Drigg, or 2) immobilization, solidification and stabilization of the contamination where the physical nature of the soil is changed, or an 'agent' is added to the soil, to reduce the migration of the contaminants, or 3) isolation and containment of the contaminated ground to reduce contaminant migration and control potential detrimental effects to human health. Where contamination has to be removed, ex situ and in situ techniques are available which minimize the waste requiring disposal to an LLW repository. These techniques include: 1) detector-based segregation 2) soil washing by particle separations 3) oil washing with chemical leaching agents 4) electro remediation 5) phyto remediation. Although many technologies are potentially applicable, their application to the remediation of a specific contaminated site is dependent on a number of factors and related to detailed site characterization studies, results from development trials and BPEO (best practicable environmental option) studies. Those factors considered of particular importance are: 1) the clean-up target 2) technical feasibility relative to the particular site, soil and contaminant characteristics, and time frame 3) site infrastructure arrangements and needs, the working life of the site and the duration of institutional care 4) long-term monitoring arrangements for slow remedial techniques or for immobilization and containment techniques 5) validation of the remediation 6) health and

  1. Contamination of fodder and radioactivity in turkeys

    International Nuclear Information System (INIS)

    Kossakowski, S.; Olszewska, K.

    1985-01-01

    Radioactivity was determined in mixed fodder (IB, IC, IE) and in turkeys which were given that feeding stuff. In animals (25 males and 25 females) fed with the above mixed fodder for 16-24 weeks radioactivity was assessed in internal organs and in their tissues. It was found that radioactivity ranged from 322.2 Bq/kg to 190.6 Bq/kg. In males the highest contamination was found in the spleen (average 0.108 Bq/g), in skeletal muscles (0.082 Bq/g), and in the liver (0.080 Bq/g), and the lowest in the skin (0.046 Bq per 1 g). The findings indicate that radioactivity of carcasses and internal organs in turkeys fed with contamined fodder was much lower than that in fodder. 6 refs., 1 tab. (author)

  2. Soil magnetic susceptibility as indicator of radioactive contamination

    International Nuclear Information System (INIS)

    Curda, S.

    2006-01-01

    Measurement of magnetic susceptibility is a method, which is used in many areas of research. The locality Ak-Tjuz is typical example of old ecological load. One of the negative effects represents radioactive contamination. This situation is caused by environmental disaster in 1964. For useful reparation it is really necessary to determinate the surface range of contamination. And measurement of the magnetic susceptibility could be the suitable method for that kind of monitoring. (author)

  3. Radioactive contamination in environment and food in Poland in 1992

    International Nuclear Information System (INIS)

    Grabowski, D.; Muszynski, W.; Petrykowska, M.; Rubel, B.; Smagala, G.; Wilgos, J.

    1993-01-01

    The level analysis of the level of radioactive contamination in environment and food samples was carried out in Poland in 1992. The results were compared to the data from 1985-1991 period. Since the Chernobyl accident gradual decrease of contamination level has been stated. The gamma dose rate and the contamination of air, fallout, tap and surface water were at the level of 1985. Still higher contamination level of cesium isotopes in soil has been reported and as a consequence food contamination was higher particularly the animal food. Actually, the source of additional dose is ingestion of artificial isotopes with food as a result of food contamination. The average effective dose equivalent, due to the contaminated food consumption, was estimated at the level 15 μSv for a Pole in 1992. (author). 13 refs, 6 figs, 20 tabs

  4. Airborne radioactive contamination following aerosol ventilation studies

    International Nuclear Information System (INIS)

    Mackie, A.; Hart, G.C.; Ibbett, D.A.; Whitehead, R.J.S.

    1994-01-01

    Lung aerosol ventilation studies may be accompanied by airborne contamination, with subsequent surface contamination. Airborne contamination has been measured prior to, during and following 59 consecutive 99 Tc m -diethylenetriamine pentaacetate (DTPA) aerosol studies using a personal air sampler. Airborne contamination ranging between 0 and 20 330 kBq m -3 has been measured. Airborne contamination increases with degree of patient breathing difficulty. The effective dose equivalent (EDE) to staff from ingested activity has been calculated to be 0.3 μSv per study. This figure is supported by data from gamma camera images of a contaminated staff member. However, surface contamination measurements reveal that 60% of studies exceed maximum permissible contamination limits for the hands; 16% of studies exceed limits for controlled area surfaces. (author)

  5. Radioactive contamination mapping system detailed design report

    International Nuclear Information System (INIS)

    Bauer, R.G.; O'Callaghan, P.B.

    1996-08-01

    The Hanford Site's 100 Area production reactors released radioactively and chemically contaminated liquids into the soil column. The primary source of the contaminated liquids was reactor coolant and various waste waters released from planned liquid discharges, as well as pipelines, pipe junctions, and retention basins leaking into the disposal sites. Site remediation involves excavating the contaminated soils using conventional earthmoving techniques and equipment, treating as appropriate, transporting the soils, and disposing the soils at ERDF. To support remediation excavation, disposal, and documentation requirements, an automated radiological monitoring system was deemed necessary. The RCMS (Radioactive Contamination Mapping System) was designed to fulfill this need. This Detailed Design Report provides design information for the RCMS in accordance with Bechtel Hanford, Inc. Engineering Design Project Instructions

  6. Establishing community trust at radioactively contaminated sites

    International Nuclear Information System (INIS)

    Simpson, E.

    1999-01-01

    Establishing community trust is an essential element in the successful remediation of a radioactively contaminated site. The US Environmental Protection Agency (EPA), Region 2 has been involved in the clean up of numerous radioactively contaminated Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), Resource Conservation Recovery Act (RCRA), and Formerly Utilized Site Remedial Action Program (FUSRAP) sites in New Jersey and New York. Each site presented a unique challenge which centered around establishing and, often, re-establishing the trust of the surrounding community. Thanks to the United States government's history regarding the use of radioactive materials, people question whether governmental regulators could possibly have the public's best interests in mind when it comes to addressing radioactively contaminated sites. It has been our experience that EPA can use its position as guardian of the environment to help establish public confidence in remedial actions. The EPA can even use its position to lend credibility to remedial activities in situations where it is not directly responsible for the clean-up. Some ways that we have found to instill community confidence are: establishing radioanalytical cross-check programs using EPA's National Air and Radiation Environmental Laboratory to provide analytical quality assurance; and establishing an environmental radiation monitoring program for the contaminated site and surrounding community. (author)

  7. Fluorescence Imaging Reveals Surface Contamination

    Science.gov (United States)

    Schirato, Richard; Polichar, Raulf

    1992-01-01

    In technique to detect surface contamination, object inspected illuminated by ultraviolet light to make contaminants fluoresce; low-light-level video camera views fluorescence. Image-processing techniques quantify distribution of contaminants. If fluorescence of material expected to contaminate surface is not intense, tagged with low concentration of dye.

  8. Lichens as indicators of radioactive contamination

    International Nuclear Information System (INIS)

    Biarzov, L.

    1993-01-01

    Samples of lichens were investigated, collected in 1987 in the Eastern Urals and in 1988 in the vicinity of Chernobyl. Data are given on the size of thalli of epiphytic lichens from trunks of pine in the Chernobyl area, and on the beta activity in epiphytic lichens in the birch forests of the Urals 30 years after the Kyshtym accident, as well as concentrations of 40 K, 106 Ru, 134 Cs, 137 Cs, and 144 Ce in lichen thalli and the bark of pine tree, taken at 5 locations in the vicinity of Chernobyl 1000 days after the accident. Also given are cross-ratios of radioactivity of 106 Ru, 134 Cs, 137 Cs, and 144 Ce in lichen thalli and in the bark of pine trees. The results indicate that the activity of radionuclides in lichen thalli make a fairly reliable indicator of relative differences between the investigated areas in terms of the level of surface contamination and qualitative composition of the involved radionuclides. (J.B.) 4 tabs., 15 refs

  9. Radioactive contamination of sewage sludge. Preliminary data

    Energy Technology Data Exchange (ETDEWEB)

    Soeder, C J; Zanders, E; Raphael, T

    1986-01-01

    Because of the radioactivity released through the explosion of the nuclear reactor near Chernobyl radionuclides have been accumulated to a significant extent in sewage sludge in the Federal Republic of Germany. This is demonstrated for samples from four activated sludge plants according to a recent recommendation of the German Commission for Radiation Protection, there is until now no reason to deviate from the common practices of sludge disposal or incineration. The degree of radioactive contamination of plant materials produced on farm lands on which sewage sludge is being spread cannot be estimated with sufficient certainty yet. Additional information is required.

  10. Radioactive contamination in monitors received for calibration

    International Nuclear Information System (INIS)

    Dias, Paulo S.; Santos, Gilvan C. dos; Brunelo, Maria Antonieta G.; Paula, Tiago C. de; Pires, Marina A.; Borges, Jose C.

    2013-01-01

    The Calibration Laboratory - LABCAL, from the Research Center for Metrology and Testing - METROBRAS, MRA Comercio de Instrumentos Eletronicos Ltda., began activities in October 2008 and, in August 2009, decided to establish a procedure for monitoring tests, external and internal, of all packages received from customers, containing instruments for calibration. The aim was to investigate possible contamination radioactive on these instruments. On July 2011, this procedure was extended to packagings of personal thermoluminescent dosemeters - TLD, received by the newly created Laboratory Laboratorio de Dosimetria Pessoal - LDP . In the monitoring procedure were used monitors with external probe, type pancake, MRA brand, models GP - 500 and MIR 7028. During the 37 months in which this investigation was conducted, were detected 42 cases of radioactive contamination, with the following characteristics: 1) just one case was personal dosimeter, TLD type; 2) just one case was not from a packing from nuclear medicine service - was from a mining company; 3) contamination occurred on packs and instruments, located and/or widespread; 4) contamination values ranged from slightly above the level of background radiation to about a thousand fold. Although METROBRAS has facilities for decontamination, in most cases, especially those of higher contamination, the procedure followed was to store the contaminated material in a room used for storage of radioactive sources. Periodically, each package and/or instrument was monitored, being released when the radiation level matched the background radiation. Every contamination detected, the client and/or owner of the instrument was informed. The Brazilian National Energy Commission - CNEN, was informed, during your public consultation for reviewing the standard for nuclear medicine services, held in mid-2012, having received from METROBRAS the statistical data available at the time. The high frequency of contamination detected and the high

  11. Radioactive contamination of aquatic media and organisms

    International Nuclear Information System (INIS)

    Fontaine, Y.

    1960-01-01

    After a brief account of the radioactive wastes produced by peaceful or military uses of Atomic Industry, the author first describes a series of observations carried out 'in the field' on the extent of contamination in aquatic organisms with respect to that of the medium. The experimental studies are then analysed, with reference both to the radioisotope metabolism and to the factors and types of contamination of aquatic organisms by wastes from atomic industry. A precise experimental project is presented at the end of the paper, including almost 300 references. (author) [fr

  12. Radioactive contamination of natural and artificial materials

    International Nuclear Information System (INIS)

    Kovalchuk, E.L.; Pomansky, A.A.; Smolnikov, A.A.; Temmoev, A.H.

    1980-01-01

    The gamma radiation of different materials was measured in an underground low-background chamber with extraordinary background characteristics. The excellent background conditions of the measurements enabled investigators to see the alpha-particle peaks of the internal radioactive contamination of NaI(Tl) detectors, which were especially made for these measurements. The sensitivity limit of the installation was determined by the internal contamination of the NaI(Tl) detectors alone. Any radiation background, except for three substances, tungsten, copper, and brass, could be registered

  13. An overview of sites contaminated by radioactivity

    International Nuclear Information System (INIS)

    Eisenbud, M.

    1991-01-01

    This paper discusses contamination of land and water by radioactive material which is a subject that has been receiving widespread media attention, and has become the cause of much public anxiety. The contaminated sites can be divided broadly into three groups: Those that are quite old, relatively small in size, and the legacy of non-nuclear industrial activities involved with natural radioactivity, mostly in the early part of the century; the chain of uranium extraction plants used during and shortly after World War II, and the plants and laboratories that comprise the Department of Energy (DOE) research and weapons production complex today. It is the latter group that is the focus of greatest public attention at the present time

  14. Method of decontaminating radioactive-contaminated instruments

    International Nuclear Information System (INIS)

    Urata, Megumu; Fujii, Masaaki; Kitaguchi, Hiroshi.

    1982-01-01

    Purpose: To enable safety processing of liquid wastes by recovering radioactive metal ions remaining in the electrolytes after the decontamination procedure thereby decreasing the radioactivity. Method: In a decontamination tank containing electrolytes consisting of diluted hydrochloric acid and diluted sulfuric acid, are provided a radioactive contaminated instrument connected to an anode and a collector electrode made of stainless steel connected to a cathode respectively. Upon applying electrical current, the portion of the mother material to be decontaminated is polished electrolytically into metal ions and they are deposited as metal on the collection electrode. After completion of the decontamination, an ultrasonic wave generator is operated to strip and remove the oxide films. Thereafter, the anode is replaced with the carbon electrode and electrical current is supplied continuously, whereby the remaining metal ions are deposited and recovered as the metal on the collection electrode. (Yoshino, Y.)

  15. Method of decontaminating radioactive-contaminated instruments

    Energy Technology Data Exchange (ETDEWEB)

    Urata, M; Fujii, M; Kitaguchi, H

    1982-03-29

    Purpose: To enable safety processing of liquid wastes by recovering radioactive metal ions remaining in the electrolytes after the decontamination procedure thereby decreasing the radioactivity. Method: In a decontamination tank containing electrolytes consisting of diluted hydrochloric acid and diluted sulfuric acid, are provided a radioactive contaminated instrument connected to an anode and a collector electrode made of stainless steel connected to a cathode respectively. Upon applying electrical current, the portion of the mother material to be decontaminated is polished electrolytically into metal ions and they are deposited as metal on the collection electrode. After completion of the decontamination, an ultrasonic wave generator is operated to strip and remove the oxide films. Thereafter, the anode is replaced with the carbon electrode and electrical current is supplied continuously, whereby the remaining metal ions are deposited and recovered as the metal on the collection electrode.

  16. Radioactive contamination level of vehicles resulted from transporting fine rare-earth minerals by rail

    International Nuclear Information System (INIS)

    Han Kaichun; Yu Boyong; Gao Shengwei

    1997-01-01

    This paper presents monitoring results of radioactive contamination level of steel open wagon surface resulted from transporting fine rare-earth minerals. Under promising transport conditions (the packaging consists of two layers of plastic bags and two layers of plastic net sacks, each package contains 50 kg of minerals, each vehicle carries 60 t), the surface radioactivity (total α and total β) of 16 vehicles on two lines from Baotou to Wujiachuan (924 km) and from Baotou to Sankeshu (2236 km) was measured before loading, after unloading and washing, using α and β surface contamination detector. The results showed that the radioactive contamination level of the vehicle surface after unloading appeared significantly different. The contamination level of vehicle bases was higher than that of both sides, long distance vehicles was higher than that of short distance vehicles. The radioactive contamination level of vehicles surface after washing was below the standard limits, these vehicles can be used for ordinary goods transport

  17. PROCESS OF DECONTAMINATING MATERIAL CONTAMINATED WITH RADIOACTIVITY

    Science.gov (United States)

    Overholt, D.C.; Peterson, M.D.; Acken, M.F.

    1958-09-16

    A process is described for decontaminating metallic objects, such as stainless steel equipment, which consists in contacting such objects with nltric acid in a concentration of 35 to 60% to remove the major portion of the contamination; and thereafter contacting the partially decontaminated object with a second solution containing up to 20% of alkali metal hydroxide and up to 20% sodium tartrate to remove the remaining radioactive contaminats.

  18. Radioactive contamination incidents involving protective clothing

    International Nuclear Information System (INIS)

    Reichelt, R.A.; Clay, M.E.; Eichorst, A.J.

    1998-01-01

    The study focuses on incidents at Department of Energy facilities involving the migration of radioactive contaminants through protective clothing. The authors analyzed 68 occurrence reports for the following factors: (1) type of work, (2) working conditions, (3) type of anti-contamination material; (4) area of body or clothing contaminated; and (5) nature of spread of contamination. A majority of reports identified strenuous work activities such as maintenance, construction, or decontamination and decommissioning projects. The reports also indicated adverse working conditions that included hot and humid or cramped work environments. The type of anti-contamination clothing most often identified was cotton or water-resistant disposable clothing. Most of the reports also indicated contaminants migrating through perspiration-soaked areas, typically in the knees and forearms. On the basis of their survey, the authors recommend the use of improved engineering controls and resilient, breathable, waterproof protective clothing for work in hot, humid, or damp areas where the possibility of prolonged contact with contamination cannot be easily avoided or controlled. 1 ref., 6 figs., 1 tab

  19. Radioactive contamination of the Yenisei River

    International Nuclear Information System (INIS)

    Vakulovsky, S.M.; Kryshev, I.I.; Nikitin, A.I.; Savitsky, Y.V.; Malyshev, S.V.; Tertyshnik, E.G.

    1995-01-01

    Based on observational data in the period 1971-1993, radioactive contamination of the Yenisei River ecosystem was analysed within 2000 km of the site of discharges from the Krasnoyarsk Mining and Chemical Industrial Complex. Data on the content of 24 Na, 32 P, 46 Sc, 51 Cr, 54 Mn, 56 Mn, 58 Co, 60 Co, 59 Fe, 65 Zn, 90 Sr, 95 Zr, 95 Nb, 103 Ru, 106 Ru, 134 Cs, 137 Cs, 140 Ba, 141 Ce, 144 Ce and 239 Np in the river ecosystem components were generalised. Radioactive contamination of water in the near zone of discharges (within 15 km) was shown to be determine mainly by the short-lived nuclides, such as 24 Na, 32 P, 56 Mn and 239 Np, as well as 51 Cr. Outside the near zone the water contamination level decreased appreciably. According to observational data of 1973, the total contamination inventory of the river bottom in the near zone was as great as 5800 kBq m -2 . More than half was accounted for by two radionuclides: 51 Cr and 65 Zn. At a distance of 1930 km from the site of discharges a technogenic activity of bottom sediments amounted to 5 kBq m -2 and was accounted for by 137 Cs and 65 Zn. The main radionuclide accumulated in fish was 32 P. Exposure doses to aquatic organisms and population were assessed in the near and far zones of the Krasnoyarsk radioactive contamination trace. Within 250 km of the site of discharges the exposure dose to the population from a consumption of 1 kg of fish was shown to amount to an average of 10 μSv. (author)

  20. Measurement of radioactive soil contamination from the air

    International Nuclear Information System (INIS)

    Loman, A.C.; Kuile, C.R. ter; Slaper, H.

    1990-09-01

    In-situ gamma spectrometry can be used to determine the qualitative and quantitative deposition of radioactive materials on the ground surface. By applying the in-situ spectrometry method using either a helicopter or an airplane, large areas can be scanned in a short period of time. In this report the results of in-situ gamma spectroscopic measurements taken from a helicopter are described. Measurements were carried out using a single point source, a field of 36 point sources, and using the present ground contamination due to fall-out from the Chernobyl accident and atom bombs. The results of these measurements were used to determine calibration factors, which were in agreement with a calibration obtained using more simple (and less expensive) laboratory measurements in combination with flux calculations. Detection limits for the measurement of surface contamination were determined. At a height of 50 meters above the surface and using a measurement time of 2 minutes, the minimally detectable surface contamination was 1.1 kBqm -2 for a Cs-137 contamination and 2.1 kBqm -2 for I-131 contamination. Fall-out determinations based on measurements taken at a height of 50 meters were in agreement with determinations taken at a height of 1 meter, and with the results obtained measuring soil samples. The in-situ gamma spectroscopy, using helicopter or airplane, is a fast and powerful method for mapping surface contamination. (author). 13 refs.; 18 figs.; 13 tabs

  1. Phytoremediation options for radioactively contaminated sites evaluated

    International Nuclear Information System (INIS)

    Vandenhove, Hildegarde

    2013-01-01

    Highlights: ► We present an overview of the most important site and environmental radioactive contamination problems encountered. ► The potential role of different phytomanagement options is discussed and illustrated with examples. ► The phytomanagement options considered are: soil phytoextraction, rhizofiltration, wetlands and alternative land use. - Abstract: The application of nuclear energy and the use of radionuclides for industrial, medical and research purposes have caused significant contamination of certain sites and their environment, which could result in health problems for several centuries if nothing is undertaken to remedy these situations. Except for the immediate environment of the facility, where decontamination activities may be feasible and affordable, the contamination often extents over a vast area and decontamination would be costly and could result in vast amounts of waste. Therefore, more realistic yet efficient remediation options should be searched for of which phytomanagement is among the potential options. A number of phytomanagement approaches will be discussed

  2. Radioactive contamination incidents involving protective clothing

    International Nuclear Information System (INIS)

    Reichelt, R.; Clay, M.; Eichorst, J.

    1996-10-01

    The study focuses on incidents at Department of Energy (DOE) facilities involving the migration of radioactive contaminants through protective clothing. The authors analyzed 68 occurrence reports for the following factors: (1) type of work; (2) working conditions; (3) type of anti-contamination (anti-C) material; (4) area of body or clothing contaminated; and (5) nature of spread of contamination. A majority of reports identified strenuous work activities such as maintenance, construction, or decontamination and decommissioning (D ampersand D) projects. The reports also indicated adverse working conditions that included hot and humid or cramped work environments. The type of anti-C clothing most often identified was cotton or water-resistant, disposable clothing. Most of the reports also indicated contaminants migrating through perspiration-soaked areas, typically in the knees and forearms. On the basis of their survey, the authors recommend the use of improved engineering controls and resilient, breathable, waterproof protective clothing for work in hot, humid, or damp areas where the possibility of prolonged contact with contamination cannot be easily avoided or controlled

  3. Radioactive contamination incidents involving protective clothing

    Energy Technology Data Exchange (ETDEWEB)

    Reichelt, R.; Clay, M.; Eichorst, J.

    1996-10-01

    The study focuses on incidents at Department of Energy (DOE) facilities involving the migration of radioactive contaminants through protective clothing. The authors analyzed 68 occurrence reports for the following factors: (1) type of work; (2) working conditions; (3) type of anti-contamination (anti-C) material; (4) area of body or clothing contaminated; and (5) nature of spread of contamination. A majority of reports identified strenuous work activities such as maintenance, construction, or decontamination and decommissioning (D&D) projects. The reports also indicated adverse working conditions that included hot and humid or cramped work environments. The type of anti-C clothing most often identified was cotton or water-resistant, disposable clothing. Most of the reports also indicated contaminants migrating through perspiration-soaked areas, typically in the knees and forearms. On the basis of their survey, the authors recommend the use of improved engineering controls and resilient, breathable, waterproof protective clothing for work in hot, humid, or damp areas where the possibility of prolonged contact with contamination cannot be easily avoided or controlled.

  4. Criteria for the designation of radioactively contaminated land

    International Nuclear Information System (INIS)

    Titley, J.; Mobbs, S.; Burgess, P.; Hitchins, G.; Sinclair, P.

    1999-01-01

    This report examines the criteria for the designation of radioactively contaminated land. It should be read in conjunction with reference to another output from the project i.e. Environment Agency report, Technical Support Material for the Regulation of Radioactively Contaminated Land 1999. This report deals with the intervention on radioactively contaminated sites i.e. where no change of land use is anticipated and where the land has become contaminated as a result of previous land use and not current practices. (author)

  5. Ecological Role of Soils upon Radioactive Contamination

    Science.gov (United States)

    Tsvetnov, Evgeny; Shcheglov, Alexei; Tsvenova, Olga

    2016-04-01

    The ecological role of soils upon radioactive contamination is clearly manifested in the system of notions about ecosystems services, i.e., benefits gained by humans from ecosystems and their components, including soils (Millennium Ecosystem Assessment, 2005). For the soils, these services are considered on the basis of soil functions in the biosphere that belong to the protective ecosystem functions within the group of soil functions known under the names of "Buffer and protective biogeocenotic shield" (at the level of particular biogeocenoses) and "Protective shield of the biosphere" (at the global biospheric level) (according to Dobrovol'skii & Nikitin, 2005). With respect to radionuclides, this group includes (1) the depositing function, i.e., the accumulation and long-term sequestration of radioactive substances by the soil after atmospheric fallout; (2) the geochemical function, i.e., the regulation of horizontal and vertical fluxes of radionuclides in the system of geochemically conjugated landscapes and in the soil-groundwater and soil-plant systems; and (3) the dose-forming function that is manifested by the shielding capacity of the soil with respect to the external ionizing radiation (lowering of the dose from external radiation) and by the regulation of the migration of radionuclides in the trophic chain (lowering of the dose from internal radiation). The depositing and geochemical functions of the soils are interrelated, which is seen from quantitative estimates of the dynamics of the fluxes of radionuclides in the considered systems (soil-plant, soil-groundwater, etc.). The downward migration of radionuclides into the lower soil layers proceeds very slowly: for decades, more than 90% of the pool of radionuclides is stored in the topmost 10 cm of the soil profile. In the first 3-5 years after the fallout, the downward migration of radionuclides with infiltrating water flows decreases from several percent to decimals and hundredths of percent from the

  6. Characteristics of radioactive contamination of vegetables derived from the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Shiba, Kazuhiro; Kitamura, Yoji; Kozaka, Takashi; Uno, Izumi; Shimizu, Kikuo; Hirota, Masahiro; Higaki, Shogo; Masumoto, Kazuyoshi

    2012-01-01

    We examined the characteristics of the radioactive contamination and the physical removal of radioactivity from contaminated cabbage and spinach. In a distribution imaging study, there were two types of contamination, spot type and spread type, of cabbage and spinach. The relative radioactivity (PSL) of the face of the leaf was much higher than that of the back of a leaf of cabbage. The ratio of relative radioactivity (PSL) between spot contamination and spread contamination in a leaf of spinach was 9.4% and 90.6%, respectively. More than 80% of radioactivity attaches to the surface of leaves of spinach. There was no significant difference of radioactivity removal between hand-washing and rinsing with running water. The degree of removal of radioactivity from contaminated spinach depended on the length of time between contamination and rinsing. When contaminated spinach was rinsed within 1 week after contamination, the removal ratio of 131 I and 137 Cs was high, with 50% and 70%, respectively. When rinsing contaminated spinaches more than 2 weeks after contamination, the removal ratio of 131 I and 137 Cs was low, approximately 34% and 69%, respectively. (author)

  7. Phytoremediation of water bodies contaminated with radioactive heavy metal

    International Nuclear Information System (INIS)

    Yan Zhen; Yuan Shichao; Ling Hui; Xie Shuibo

    2012-01-01

    The sources of the radioactive heavy metal in the water bodies were analyzed. The factors that affect phyto remediation of water contaminated with radioactive heavy metal were discussed. The plant species, mechanism and major technology of phyto remediation of water contaminated with radioactive heavy metal were particularly introduced. The prospective study was remarked. (authors)

  8. Environmental radioactive contamination and its control for nuclear power plants

    International Nuclear Information System (INIS)

    Shi Zhongqi; Qu Jingyuan; Cui Yongli

    1998-01-01

    The environmental radioactive releases and exposure to human being due to operation of nuclear power plants in the world and in China, environmental contamination and consequences caused by severe nuclear power plant accidents in the history, control of the radioactive contamination in China, and some nuclear laws on the radioactive contamination control established by international organizations and USA etc. are described according to literature investigation and research. Some problems and comments in radioactive contamination control for nuclear power plants in China are presented. Therefore, perfecting laws and regulations and enhancing surveillances on the contamination control are recommended

  9. [Decorporation agents for internal radioactive contamination].

    Science.gov (United States)

    Ohmachi, Yasushi

    2015-01-01

    When radionuclides are accidentally ingested or inhaled, blood circulation or tissue/organ deposition of the radionuclides causes systemic or local radiation effects. In such cases, decorporation therapy is used to reduce the health risks due to their intake. Decorporation therapy includes reduction and/or inhibition of absorption from the gastrointestinal tract, isotopic dilution, and the use of diuretics, adsorbents, and chelating agents. For example, penicillamine is recommended as a chelating agent for copper contamination, and diethylene triamine pentaacetic acid is approved for the treatment of internal contamination with plutonium. During chelation therapy, the removal effect of the drugs should be monitored using a whole-body counter and/or bioassay. Some authorities, such as the National Council on Radiation Protection and Measurements and International Atomic Energy Agency, have reported recommended decorporation agents for each radionuclide. However, few drugs are approved by the US Food and Drug Administration, and many are off-label-use agents. Because many decontamination agents are drugs that have been available for a long time and have limited efficacy, the development of new, higher-efficacy drugs has been carried out mainly in the USA and France. In this article, in addition to an outline of decorporation agents for internal radioactive contamination, an outline of our research on decorporation agents for actinide (uranium and plutonium) contamination and for radio-cesium contamination is also presented.

  10. Survey of radioactive contamination of foodstuffs

    International Nuclear Information System (INIS)

    Lee, W. R.; Lee, C. W.; Choi, G. S.; Cho, Y. H.; Kang, M. J.; Cheong, K. H.; Kim, H. R.; Kwak, J. Y.

    2005-11-01

    The purpose of this study is to survey and assess radioactive contamination of foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Based on survey and assessment, final goal is to improve the public health by radiation protection. Sampled foodstuffs items are collected from the markets : one group are imported foodstuffs and the other group are domestic foodstuffs producted around nuclear facilities. After pretreatments such as drying, ashing, and homogenization, all samples were analyzed by gamma spectrometer system. The 137 Cs radionuclide was only measured among the regulation radionuclides ( 137 Cs, 134 Cs, 131 I) of food code. All radionuclides of the domestic foodstuffs collected around nuclear facilities were below Minimum Detectable Activity (MDA). But the activity concentrations of Inonotus obliquus (Chaga mushooms) from Russia ranged up to 171.27 (average value : 36.65) Bq/kg-fresh. In the case of blueberry jam, the radioactivity of 137 Cs is higher than expected value. Other samples are below MDA except some spices. Based on the previous and present results, it should be strengthen to survey for Inontus obliquus (Chaga mushooms), of which the radioactivity shows the range from MDA up to 800.01 Bq/kg-fresh. It should assess the public radiation exposure via food chain because it has the excess provability of the maximum permitted level of food code, which is regulation of KFDA. The development method based on international standard would be used at radioactive analysis as well as education of practical workers and it could be applied as the basis data for amending the analysis method of food code. Our country only surveys gamma emitting radionuclides till now but international organization or foreign countries for example EU survey alpha and beta emitting radionuclides as well as gamma emitting radionuclides. So our country should also research necessity of survey for alpha and beta emitting radionuclides

  11. Survey of radioactive contamination of foodstuffs

    Energy Technology Data Exchange (ETDEWEB)

    Lee, W. R.; Lee, C. W.; Choi, G. S.; Cho, Y. H.; Kang, M. J.; Cheong, K. H.; Kim, H. R.; Kwak, J. Y

    2005-11-15

    The purpose of this study is to survey and assess radioactive contamination of foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Based on survey and assessment, final goal is to improve the public health by radiation protection. Sampled foodstuffs items are collected from the markets : one group are imported foodstuffs and the other group are domestic foodstuffs producted around nuclear facilities. After pretreatments such as drying, ashing, and homogenization, all samples were analyzed by gamma spectrometer system. The {sup 137}Cs radionuclide was only measured among the regulation radionuclides ({sup 137}Cs, {sup 134}Cs, {sup 131}I) of food code. All radionuclides of the domestic foodstuffs collected around nuclear facilities were below Minimum Detectable Activity (MDA). But the activity concentrations of Inonotus obliquus (Chaga mushooms) from Russia ranged up to 171.27 (average value : 36.65) Bq/kg-fresh. In the case of blueberry jam, the radioactivity of {sup 137}Cs is higher than expected value. Other samples are below MDA except some spices. Based on the previous and present results, it should be strengthen to survey for Inontus obliquus (Chaga mushooms), of which the radioactivity shows the range from MDA up to 800.01 Bq/kg-fresh. It should assess the public radiation exposure via food chain because it has the excess provability of the maximum permitted level of food code, which is regulation of KFDA. The development method based on international standard would be used at radioactive analysis as well as education of practical workers and it could be applied as the basis data for amending the analysis method of food code. Our country only surveys gamma emitting radionuclides till now but international organization or foreign countries for example EU survey alpha and beta emitting radionuclides as well as gamma emitting radionuclides. So our country should also research necessity of survey for alpha and beta emitting

  12. Radioactive Probes on Ferromagnetic Surfaces

    CERN Multimedia

    2002-01-01

    On the (broad) basis of our studies of nonmagnetic radioactive probe atoms on magnetic surfaces and at interfaces, we propose to investigate the magnetic interaction of magnetic probe atoms with their immediate environment, in particular of rare earth (RE) elements positioned on and in ferromagnetic surfaces. The preparation and analysis of the structural properties of such samples will be performed in the UHV chamber HYDRA at the HMI/Berlin. For the investigations of the magnetic properties of RE atoms on surfaces Perturbed Angular Correlation (PAC) measurements and Mössbauer Spectroscopy (MS) in the UHV chamber ASPIC (Apparatus for Surface Physics and Interfaces at CERN) are proposed.

  13. 10 CFR 39.69 - Radioactive contamination control.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Radioactive contamination control. 39.69 Section 39.69... Radiation Safety Requirements § 39.69 Radioactive contamination control. (a) If the licensee detects evidence that a sealed source has ruptured or licensed materials have caused contamination, the licensee...

  14. Thule-2003 - Investigation of radioactive contamination

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Sven P.; Roos, P.

    2006-05-15

    Analyses of marine and terrestrial samples collected in August 2003 from Bylot Sound at Thule, Northwest Greenland, show that plutonium from nuclear weapons in the American B52 plane, which crashed on the sea ice in January 1968, persists in the environment. The highest concentrations of plutonium are found in the marine sediments under the location where the plane crashed. The distribution of plutonium in the marine sediment is very inhomogeneous and associated with hot particles with activities found up to 1500 Bq {sup 239,240}Pu. Sediment samples collected in Wolstenholme Fjord north of the accident site show plutonium concentrations, which illustrates the redistribution of plutonium after the accident. The total plutonium inventory in the sediments has been assessed based on systematic analyses considering hot particles. The inventory of {sup 239,240}Pu in the sediments within a distance of 17 km from the point of impact of the B52 plane is estimated at 2.9 TBq (1 kg). Earlier estimates of the inventory were approximately 1.4 TBq {sup 239,240}Pu. Seawater and seaweed samples show increased concentrations of plutonium in Bylot Sound. The increased concentrations are due to resuspension of plutonium-containing particles from the seabed and transport further away from the area. Plutonium concentrations in seawater, seaweed and benthic animals in Bylot Sound are low but clearly above background levels. All soil samples collected from Narssarssuk show accident plutonium with levels above background. Plutonium is very inhomogeneously distributed and associated with particles in the surface layers. Hot particles were found in soil with activities up to 150 Bq {sup 239,240}Pu. Plutonium in the marine environment at Thule presents an insignificant risk to man. Most plutonium remains in the seabed under Bylot Sound far from man under relatively stable conditions and concentrations of plutonium in seawater and animals are low. However, the plutonium contamination of

  15. Thule-2003 - Investigation of radioactive contamination

    International Nuclear Information System (INIS)

    Nielsen, Sven P.; Roos, P.

    2006-05-01

    Analyses of marine and terrestrial samples collected in August 2003 from Bylot Sound at Thule, Northwest Greenland, show that plutonium from nuclear weapons in the American B52 plane, which crashed on the sea ice in January 1968, persists in the environment. The highest concentrations of plutonium are found in the marine sediments under the location where the plane crashed. The distribution of plutonium in the marine sediment is very inhomogeneous and associated with hot particles with activities found up to 1500 Bq 239,240 Pu. Sediment samples collected in Wolstenholme Fjord north of the accident site show plutonium concentrations, which illustrates the redistribution of plutonium after the accident. The total plutonium inventory in the sediments has been assessed based on systematic analyses considering hot particles. The inventory of 239,240 Pu in the sediments within a distance of 17 km from the point of impact of the B52 plane is estimated at 2.9 TBq (1 kg). Earlier estimates of the inventory were approximately 1.4 TBq 239,240 Pu. Seawater and seaweed samples show increased concentrations of plutonium in Bylot Sound. The increased concentrations are due to resuspension of plutonium-containing particles from the seabed and transport further away from the area. Plutonium concentrations in seawater, seaweed and benthic animals in Bylot Sound are low but clearly above background levels. All soil samples collected from Narssarssuk show accident plutonium with levels above background. Plutonium is very inhomogeneously distributed and associated with particles in the surface layers. Hot particles were found in soil with activities up to 150 Bq 239,240 Pu. Plutonium in the marine environment at Thule presents an insignificant risk to man. Most plutonium remains in the seabed under Bylot Sound far from man under relatively stable conditions and concentrations of plutonium in seawater and animals are low. However, the plutonium contamination of surface soil at

  16. Radioactive contamination, what actions for the polluted sites; Contamination radioactive, quelles actions pour les sites pollues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The nuclear safety authority and the direction of prevention of pollutions and risks have organised the first edition of the national colloquium: radioactive contamination: what actions for polluted sites. Four axes can be taken to follow this colloquium: prevention, outstanding tools to evaluate risks and rehabilitation, a better responsibility of operators and memory keeping. (N.C.)

  17. Packaging and transportation of radioactively contaminated lead

    International Nuclear Information System (INIS)

    Gleason, Eugene; Holden, Gerard

    2007-01-01

    Under the management of the Nuclear Decommissioning Authority (NDA) the government of the United Kingdom has launched an ambitious program to remediate the nation's nuclear waste legacy. Over a twenty-five year period NDA plans to decommission several first generation nuclear power plants and other radioactive facilities. The use innovative, safe 'fit for purpose' technologies will be a major part of this complex program. This paper will present a case study of a recently completed project undertaken in support of the nuclear decommissioning activities at the Sellafield site in the United Kingdom. The focus is on an innovative application of new packaging technology developed for the safe transportation of radioactively contaminated lead objects. Several companies collaborated on the project and contributed to its safe and successful conclusion. These companies include British Nuclear Group, Gravatom Engineering, W. F. Bowker Transport, Atlantic Container Lines, MHF Logistical Solutions and Energy Solutions. New containers and a new innovative inter-modal packaging system to transport the radioactive lead were developed and demonstrated during the project. The project also demonstrated the potential contribution of international nuclear recycling activities as a safe, economic and feasible technical option for nuclear decommissioning in the United Kingdom. (authors)

  18. Measurement and removal of surface contamination

    International Nuclear Information System (INIS)

    Neider, M.; Tamberg, T.

    1990-01-01

    This is a critical reappraisal of the sampling factor which is important for indirect contamination measurement. The factor gives the radioactivity collected by means of a wipe sample as a fraction of the total loose radioactivity i.e. without firm adhesion. It is used in national and international standard specifications and stated, frequently with excessive conservatism, as 0.1. Secondly, the standard specifications for the testing and appraisal of surface materials in relation to their decontamination capacity and for testing the effect of decontamination agents hitherto bond and Co-60 and Cs-137 are to be expanded to include radioactive iodine, which is important in nuclear medicine. The selection of optimum surface materials will thus be put on an improved basis. (orig./DG) [de

  19. Description of measurement techniques for surface contaminations

    International Nuclear Information System (INIS)

    Bourrez, E.

    2001-01-01

    The needs of evaluation of the surface contamination are numerous in the processes of production and management of radioactive waste. The market of radiation protection materials proposes a lot of devices answering to the almost all these needs. These device have however their conditions and particular limits for use. To realize correct measurements it is use the device, the technique and the methods adapted to the need, by taking into account the optimization of economical aspect. (N.C.)

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  3. Radioactive elements and earthworms in contaminated soils

    International Nuclear Information System (INIS)

    Suleymanova, A.S.; Abdullayev, A.S.; Ahmadov, G.S.; Naghiyev, J.A.; Samadov, P.A.

    2010-11-01

    Earthworms are one of the indispensable soil animals which treat soil with letting it through their gut and help increasing soil fertility. The effect of radioactive elements and comparative effect of heavy metals to the vital functions of earthworms were determined in laboratory conditions. Experiments were continued for a month, and first of all, each soil type, grey-brown soil from Ramana iodine plant territory of Baku city, brown soil from Aluminum plant territory of Ganja city, aborigine grey-brown soil of Absheron peninsula, treated with Ra and U salts as model variants and brown soil of Ganja city was analyzed by gamma-spectrometer for radionuclide determining at the beginning and at the end of the experiment. Earthworms (Nicodrilus Caliginosus Sav.trapezoides) aboriginal for Absheron peninsula and plant residues were added to the soil. At the end of the month the biomass, survival value, coprolite allocation value, food activity and catalase value in earthworms and in soil were determined. The gamma-spectrometric analysis results gave interesting values in coprolites, soils which had been treated through the earthworms' gut. In comparison with the initial variants in experimental results more percent of radioactivity was gathered in coprolites. By this way earthworms absorbed most of radioactive elements and allocated them as coprogenous substances on the upper layer of soil. During absorbing, some percents of radioactive elements were also gathered in gut cells of the earthworms. Thereby determination of some vital functions of earthworms was expedient. Thus, by the instrumentality of these experiments we can use earthworms for biodiagnosis and for bioremediation of contaminated soils with radionuclides and heavy metals.

  4. Radioactive contamination in the Arctic - Present situation and future challenges

    International Nuclear Information System (INIS)

    Strand, P.

    2002-01-01

    There is currently a focus on radioactivity and the Arctic region. The reason for this is the high number of nuclear sources in parts of the Arctic and the vulnerability of Arctic systems to radioactive contamination. The Arctic environment is also perceived as a wilderness and the need for the protection of this wilderness against contamination is great. In 1991, the International Arctic Environmental Protection Strategy (IAEPS) was launched and the Arctic Monitoring and Assessment Programme (AMAP) established. AMAP is undertaking an assessment of the radioactive contamination of the Arctic and its radiological consequences. This paper summarises some of current knowledge about sources of radioactive contamination, vulnerability, exposure of man, and potential sources for radioactive contamination within Arctic and some views on the future needs for work concerning radioactivity in Arctic. (author)

  5. Ways for forestry management in radioactive contamination zone

    International Nuclear Information System (INIS)

    Kaletnik, N.N.; Pasternak, P.S.; Kiselevskij, R.G.; Molotkov, P.I.; Kuchma, N.D.; Landin, V.P.; Matukhno, Yu.D.; Shlonchak, G.L.; Podkur, P.P.; Khudolej, V.I.

    1989-01-01

    The necessity of realization of forestry protection measures in the radioactive contamination zone is determined by the forest ecological part and the problems of elimination of the territory secondary contamination in the process of radionuclide migration. The damage of forest tracts in the zone is analyzed. The data on pine surface contamination levels, needles appearance in forests with different degree of damage and crown phytomass, growth for pines 20 years old in forests with different damage degrees are considered. The index of pine forest state is obtained. The data discussed reveal the complicated situation, which takes place in the 30-km zone forests. It is shown that the depth of radionuclide migration into soil for forest areas is twice lower as compared with that for open places. 6 tabs

  6. Radioactive Contamination of Agricultural Products in Poland

    International Nuclear Information System (INIS)

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

    2003-01-01

    Radiological contamination of the environment is caused by nuclear activities on the globe: nuclear weapon tests and the Chernobyl accident. The transfer of radionuclides to the organism via ingestion is one of the sources of doses obtained by people. To assess the doses received by humans the intake of isotopes with daily diet was defined. The concentration of radionuclides in foodstuffs was determined. The network of Service for Measurement of Radioactive Contamination systematically controls all kinds of important agricultural products such as milk, meat, vegetables, fruit, cereals and forest products: mushrooms, blueberries etc. Measurement stations involved in food monitoring act within Sanitary-Epidemiological Stations, Veterinary Hygiene Units and Chemical-Agricultural Stations. All activities are co-ordinated by the Central Laboratory for Radiological Protection. The level of activity of caesium isotopes has regularly been monitored in collected samples originating from different administrative districts of Poland. Since 1994 the 134 Cs concentration has been below the detection limit. The activity of 137 Cs has been measured to determine long-term effect of the accident on the contamination of milk, meat and other foodstuffs. (orig.)

  7. Radiological Risk Assessment and Survey of Radioactive Contamination for Foodstuffs

    International Nuclear Information System (INIS)

    Lee, W.R.; Lee, C.W.; Choi, K.S.

    2007-11-01

    After the Chernobyl nuclear accident in 1986, a radiological dose assessment and a survey of a radioactive contamination for foodstuffs have been investigated by many countries such as EU, Japan, USA. In the case of Japan which is similar to our country for the imported regions of foodstuffs, there were some instances of the excess for regulation on the maximum permitted levels of radioactive contamination among some imported foodstuffs. Concerns about the radioactive contamination of foodstuffs are increased because of the recently special situation (Nuclear test of North Korea). The purpose of this study is a radiological dose assessment and a survey of a radioactive contamination for foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Analytical results of the collected samples are below MDA. In this project, the model of radiological dose assessment via the food chain was also developed and radiological dose assessment was conducted based on surveys results of a radioactive contamination for foodstuffs in the Korean open markets since 2002. The results of radiological dose assessment are far below international reference level. It shows that public radiation exposure via food chain is well controlled within the international guide level. However, the radioactive contamination research of imported foodstuffs should be continuous considering the special situation(nuclear test of North Korea). These results are used to manage the radioactive contamination of the imported foodstuffs and also amend the regulation on the maximum permitted levels of radioactive contamination of foodstuffs

  8. Radioactive contamination of the marine environment

    International Nuclear Information System (INIS)

    Aarkrog, A.

    1997-01-01

    The major source of man-made radioactivity in the oceans is derived from nuclear weapons testing fallout, which occurred mostly in the late 1950s and early 1960s. For example, 0.9 EBq of 137 Cs and 0.6 EBq of 90 Sr were introduced in this way. Only 60% of the released activity was disposed of in the oceans, rather than 70%, because the nuclear weapons testing occurred mainly in the Northern hemisphere, and the land masses cover more of the Northern hemisphere than the Southern hemisphere. There have also been other releases into the oceans; for example, the water-borne discharges from the Sellafield reprocessing plant in the UK, which occurred from the mid-1970s to the mid-1980s. During this decade, in the order of 40 PBq of 137 Cs was discharged into the Irish sea, and from there it was transported into the north Atlantic ocean. The third important source of radioactivity was the Chernobyl accident. Although most of this radioactivity was distributed over the land masses, about 5 PBq was deposited into the Baltic Sea and about 3 PBq into the Black Sea. The radioactive debris from Chernobyl was distributed around the Northern hemisphere, so some of the radioactivity must have been deposited in the North Atlantic ocean. There have also been a number of local contaminations of the oceans. Among these are satellite failures. For example, the SNAP-9A satellite, which burned up over the South Atlantic ocean in the early 1960s, became a major source of 238 Pu pollution. This is the reason why there is an increased 238 Pu: 239 Pu ratio, mostly in the Southern hemisphere, in global fallout. There are also a number of nuclear submarines on the bottom of the sea; for example, the American Thresher submarine in the Atlantic ocean and the Comsomolets submarine in the Norwegian-Barents sea. Furthermore, there have been several accidents with nuclear weapons; for example, the Palomares accident in Spain in 1966 and the Thule accident in Greenland in 1968. Finally, nuclear

  9. Predicting the radioactive contamination of the surroundings near a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Khristova, M; Paskalev, Z

    1975-01-01

    Predicting the radioactive contamination requires determining the concentration of radioactive material emitted from the stack of a nuclear power plant into the air and deposited on the earth's surface. The main factors determining the degree of contamination are the distance from the stack, the wind velocity and air turbulence. Formulas are presented for predicting the amount of radioactivity as a function of the initial concentration of activity, the distance from the stack and the meteorological condition. Formulas are given for the maximum deposition of radioactive aerosols at a distance R from the stack under wet and dry condtions. 2 refs. (SJR)

  10. Radioactive contamination at Chelyabinsk-65, Russia

    International Nuclear Information System (INIS)

    Cochran, T.B.; Norris, R.S.; Suokko, K.L.

    1993-01-01

    As a consequence of poor waste management practices at Chelyabinsk-65, primarily during the first two decades of operations, the site and its surroundings were extensively contaminated, and thousands of people were unknowingly exposed to excessive levels of radiation. In terms of human health consequences, most of the damage has already been inflicted. Nevertheless, containment of the residual radioactivity in high-level waste tanks, in the reservoirs along the Techa River, and in and below Lake Karachay represents expensive challenges for which the best, or even adequate solutions, have yet to be devised. Russian scientists have the knowledge to address these problems, but lack practical experience with contemporary waste management practices. Western expertise could be helpful in quantifying the extent of the problems and devising solutions. However, the real challenge will be to mobilize the economic resources for effective cleanup at Chelyabinsk-65 in light of all the other economic and environmental problems Russia faces. 81 refs

  11. Low-waste technology of prevention, decontamination and localization of radioactive contamination

    International Nuclear Information System (INIS)

    Kizhnerov, L. V.; Konstantinov, Ye. A.; Prokopenko, V. A.; Sorokin, N. M.

    1997-01-01

    The report presents the results of research in developing a low-waste technology of prevention, decontamination and localization of radioactive contamination founded on the of easily removed protective polymeric coating based on water and alcohol latexes and dispersion of polymers with special activating additives. The developed technology provides for the reduction of weakly fixed radioactive contamination of non-painted and painted surfaces to admissible levels (as a rule), it securely prevents and localizes contamination and does not generate secondary liquid radioactive wastes

  12. Sources of radioactive contamination inside houses

    International Nuclear Information System (INIS)

    Sajet, A.S.

    2010-01-01

    People may be exposed at home to multiple sources of nuclear radiation such as gamma, beta and alpha rays emitters. House atmosphere is polluted with nuclear radiation from water pollutants and rocks used in the construction. Radon is the only radioactive non-metallic element. Environmental organizations estimated that all houses contain varying concentrations of radon gas, and the residents are exposed to levels of radon over the years. The source of radon in houses is uranium, which may be found in rocks of the house, soil of the garden, water of the deep artesian wells and building materials, especially granite rocks. Breathing air that contains high levels of radon causes lung cancer. Radon is the second cause of lung disease after smoking. There are many means to reduce house pollution including: utilisation of air filters to remove contaminated dust particles, keep residential areas away from the establishments that use nuclear technology or embedded by nuclear waste, avoid using materials made from asbestos in construction works and proper use and disposal of chemicals and medicines containing radioactive isotopes. (author)

  13. Radiological control in a mine with a naturally-occurring radioactive material -NORM: III assessment of removable surface contamination in a pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, W.S.; Py Junior, D.A.; Silva, A.C.A.; Garcia Filho, O., E-mail: pereiraws@gmail.com [Industrias Nucleares do Brasil (INB), Pocos de Caldas, MG (Brazil). Unidade de Tratamento de Minerio. Grupo Multidisciplinar de Radioprotecao; Kelecom, A., E-mail: akelecom@id.uff.br [Universidade Federal Fluminense (GETA/LARARA-PLS/UFF), Niteroi, RJ, (Brazil). Grupo de Estudos em Temas Ambientais. Lab. de Radiobiologia e Radiometria; Pereira, J.R.S., E-mail: pereirarsj@gmail.com [Universidade Federal de Alfenas (UNIFAL), Pocos de Caldas, MG (Brazil)

    2013-07-01

    Ore Treatment Unit (OUT) possesses a process laboratory. Considering the uranium ore processing, this laboratory works in close cooperation with the Radiation Protection Service of the Unit. In the year of 2009 a pilot plant for the development of solvent uranium extraction from the phosphate ore of the mine of Santa Quiteria city, in Ceara State, Brazil was developed. In this kind of plant the surface contamination may cause contamination for Occupational Exposed Individuals (OEI). In order to control this kind of contamination and offer a safety work's condition for OEIs, a monitoring program of transferable contamination using swab samples was developed. 162 swabs were made. For the alpha emitters the monitoring results varied from 0.001 Bq cm{sup -2} to 0.014 Bq cm{sup -2}, with average value of 0.002 Bq cm{sup -2}. For beta emitters the results varied from 0.010 Bq cm{sup -2} to 0.031 Bq cm{sup -2} with average equal to 0.011 Bq cm{sup -2}. For alpha emitters, 87.65 % of the results were below 0.004 Bq cm{sup -2}, values that are one order of magnitude smaller than the limit and the maximum value stayed in 35 % of the limit for an object to be considered contaminated. For beta emitters, 90 % of the results were below 0.010 Bq cm{sup -2} that corresponds to 25 % of the limit and 100 % were below 0.031 Bq cm{sup -2} below the limit for an object to be considered contaminated. In both cases any object monitored during the operation, was not considered contaminated, proving the good practices employed in the laboratory, resultant of the good planning of the Radiation Protection Service for the operations' process. (author)

  14. Radiological control in a mine with a naturally-occurring radioactive material -NORM: III assessment of removable surface contamination in a pilot plant

    International Nuclear Information System (INIS)

    Pereira, W.S.; Py Junior, D.A.; Silva, A.C.A.; Garcia Filho, O.

    2013-01-01

    Ore Treatment Unit (OUT) possesses a process laboratory. Considering the uranium ore processing, this laboratory works in close cooperation with the Radiation Protection Service of the Unit. In the year of 2009 a pilot plant for the development of solvent uranium extraction from the phosphate ore of the mine of Santa Quiteria city, in Ceara State, Brazil was developed. In this kind of plant the surface contamination may cause contamination for Occupational Exposed Individuals (OEI). In order to control this kind of contamination and offer a safety work's condition for OEIs, a monitoring program of transferable contamination using swab samples was developed. 162 swabs were made. For the alpha emitters the monitoring results varied from 0.001 Bq cm -2 to 0.014 Bq cm -2 , with average value of 0.002 Bq cm -2 . For beta emitters the results varied from 0.010 Bq cm -2 to 0.031 Bq cm -2 with average equal to 0.011 Bq cm -2 . For alpha emitters, 87.65 % of the results were below 0.004 Bq cm -2 , values that are one order of magnitude smaller than the limit and the maximum value stayed in 35 % of the limit for an object to be considered contaminated. For beta emitters, 90 % of the results were below 0.010 Bq cm -2 that corresponds to 25 % of the limit and 100 % were below 0.031 Bq cm -2 below the limit for an object to be considered contaminated. In both cases any object monitored during the operation, was not considered contaminated, proving the good practices employed in the laboratory, resultant of the good planning of the Radiation Protection Service for the operations' process. (author)

  15. Issues in recycling and disposal of radioactively contaminated materials

    International Nuclear Information System (INIS)

    Kluk, A.F.; Hocking, E.K.; Roberts, R.; Phillips, J.W.

    1993-01-01

    The Department of Energy's present stock of potentially re-usable and minimally radioactively contaminated materials will increase significantly as the Department's remediation activities expand. As part of its effort to minimize wastes, the Department is pursuing several approaches to recover valuable materials such as nickel, copper, and steel, and reduce the high disposal costs associated with contaminated materials. Key approaches are recycling radioactively contaminated materials or disposing of them as non-radioactive waste. These approaches are impeded by a combination of potentially conflicting Federal regulations, State actions, and Departmental policies. Actions to promote or implement these approaches at the Federal, State, or Departmental level involve issues which must be addressed and resolved. The paramount issue is the legal status of radioactively contaminated materials and the roles of the Federal and State governments in regulating those materials. Public involvement is crucial in the debate surrounding the fate of radioactively contaminated materials

  16. Radioactive substances found on the contaminated fish

    Energy Technology Data Exchange (ETDEWEB)

    Kiba, T; Ohashi, S; Shibata, M; Mizube, T

    1954-01-01

    Radiochemical investigation of the substance collected from the surface of tuna fish which were brought back by the No. 5 Fukuryu Maru was performed. Most of the radioactivity was found on the scales which could not be decontaminated by treating with H/sub 2/O; 80% of the activity was removed by washing the dried scales with 3N HCl. Paper chromatographic separation of the HCl fraction showed the presence of /sup 140/Ba, /sup 89/Sr, /sup 132/Te, and probably /sup 95/Zr, /sup 140/La, and rare earths.

  17. Contamination detector for inner surface of container

    International Nuclear Information System (INIS)

    Watanabe, Tadao.

    1995-01-01

    The present invention concerns a device for detecting contamination of radioactive materials on the inner surface of a vessel upon reutilizing the vessel for containing solidified radioactive wastes and transporting them. Namely, the detecting device has following functions. (1) A radiation detector detects the radioactive materials on the inner surface of the vessel. (2) A plurality of proximity switches measure the distance from the radiation detector to the wall surface of the vessel and are actuated if the distance is decreased to a predetermined value, (3) A vessel inner surface position calculation mechanism calculates the position of the inner surface of the vessel based on the information from a direction indicator and a height indicator. (4) A frontal limit detector detects the limit for allowing the radiation detector to proceed. (5) A vessel inner shape judging mechanism for judging the shape of the inner side of the vessel based on the signals from the proximity switches in a state where the frontal limit detector is operated and a vessel inner surface position signal outputted from the vessel inner surface position calculation mechanism. As a result, the shape of the inner side of the vessel can accurately be recognized, thereby improving accuracy of radiation measurement. (I.S.)

  18. Radioactive Ions for Surface Characterization

    CERN Multimedia

    2002-01-01

    The collaboration has completed a set of pilot experiments with the aim to develop techniques for using radioactive nuclei in surface physics. The first result was a method for thermal deposition of isolated atoms (Cd, In, Rb) on clean metallic surfaces. \\\\ \\\\ Then the diffusion history of deposited Cd and In atoms on two model surfaces, Mo(110) and Pd(111), was followed through the electric field gradients (efg) acting at the probe nuclei as measured with the Perturbed Angular Correlation technique. For Mo(110) a rather simple history of the adatoms was inferred from the experiments: Atoms initially landing at terrace sites diffuse from there to ledges and then to kinks, defects always present at real surfaces. The next stage is desorption from the surface. For Pd a scenario that goes still further was found. Following the kink stage the adatoms get incorporated into ledges and finally into the top surface layer. For all these five sites the efg's could be measured.\\\\ \\\\ In preparation for a further series o...

  19. Risk assessment methodology for evaluating releases of radioactively contaminated materials

    International Nuclear Information System (INIS)

    Chen, S.Y.

    1993-01-01

    Extensive decontamination and decommissioning (D ampersand D) activities are expected to be required in the near future in association with license termination of nuclear power facilities and cleanup efforts at the U.S. Department of Energy's (DOE's) weapons production facilities. In advance of these D ampersand D activities, it is becoming increasingly urgent that standards be established for the release of materials with residual radioactive contamination. The only standards for unrestricted release that currently exist address surface contamination. The methods used to justify those standards were developed some 20 yr ago and may not satisfy today's criteria. Furthermore, the basis of setting standards has moved away from the traditional open-quotes instrumentation-basedclose quotes concept toward a open-quotes risk-basedclose quotes approach. Therefore, as new release standards are developed, it will be necessary that risk assessment methodology consistent with modern concepts be incorporated into the process. This paper discusses recent developments in risk methodology and issues and concerns regarding the future development of standards for the release of radioactively contaminated materials

  20. Processing method for contaminated water containing radioactive waste

    International Nuclear Information System (INIS)

    Tahara, Toshiaki; Fukagawa, Ken-ichiro.

    1994-01-01

    For absorbing contaminated water containing radioactive substances, a sheet is prepared by covering water absorbing pulps carrying an organic water absorbent having an excellent water absorbability is semi-solidified upon absorption water with a water permeable cloth, such as a non-woven fabric having a shape stability. As the organic water absorbent, a hydrophilic polymer which retains adsorbed water as it is used. In particular, a starch-grafted copolymer having an excellent water absorbability also for reactor water containing boric acid is preferred. The organic water absorbent can be carried on the water absorbing pulps by scattering a granular organic water absorbent to the entire surface of the water absorbing cotton pulp extended thinly to carry it uniformly and putting them between thin absorbing paper sheets. If contaminated water containing radioactive materials are wiped off by using such a sheet, the entire sheet is semi-solidified along with the absorption with no leaching of the contaminated water, thereby enabling to move the wastes to a furnace for applying combustion treatment. (T.M.)

  1. Residual radioactive contamination from decommissioning: Technical basis for translating contamination levels to annual dose

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Peloquin, R.A.

    1990-01-01

    This document describes the generic modeling of the total effective dose equivalent (TEDE) to an individual in a population from a unit concentration of residual radioactive contamination. Radioactive contamination inside buildings and soil contamination are considered. Unit concentration TEDE factors by radionuclide, exposure pathway, and exposure scenario are calculated. Reference radiation exposure scenarios are used to derive unit concentration TEDE factors for about 200 individual radionuclides and parent-daughter mixtures. For buildings, these unit concentration factors list the annual TEDE for volume and surface contamination situations. For soil, annual TEDE factors are presented for unit concentrations of radionuclides in soil during residential use of contaminated land and the TEDE per unit total inventory for potential use of drinking water from a ground-water source. Because of the generic treatment of potentially complex ground-water systems, the annual TEDE factors for drinking water for a given inventory may only indicate when additional site data or modeling sophistication are warranted. Descriptions are provided of the models, exposure pathways, exposure scenarios, parameter values, and assumptions used. An analysis of the potential annual TEDE resulting from reference mixtures of residual radionuclides is provided to demonstrate application of the TEDE factors. 62 refs., 5 figs., 66 tabs

  2. The inhalation of radioactive materials as related to hand contamination

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, J.C.; Rohr, R.C.

    1953-09-15

    Tests performed to determine the hazard associated with the inhalation of radioactive materials as the result of smoking with contaminated hands indicate that for dry uranium compounds adhering to the palmar surfaces of the hands, approximately 1.0% of the material may be transferred to a cigarette, and that of this approximately 0.2% may appear in the smoke which is inhaled. Most of the contamination originally placed in a cigarette was found in the ash, and only 11% of the material was not recovered following burning; approximately half of this loss may be attributed to normal losses inherent in the analytical process, the recovery efficiency for which was found by supplementary experiments to be 95%.

  3. Influence of radioactive contaminants on absorbed dose estimates for radiopharmaceuticals

    International Nuclear Information System (INIS)

    Watson, E.E.; Stabin, M.G.

    1986-01-01

    Several popular radiopharmaceutical products contain low levels of radioactive contaminants. These contaminants increase the radiation absorbed dose to the patient without any increased benefit and, in some cases, with a decrease in image quality. The importance of a contaminant to the radiation dosimetry picture is a function of 1) the contaminant level, 2) the physical half-life of the contaminant, 3) the organ uptake and the biological half-time of the contaminant in the various body systems, and 4) the decay mode, energy, etc. of the contaminant. The general influence of these parameters is discussed in this paper; families of curves are included that reflect the changing importance of contaminant dosimetry with respect to the primary radionuclide as a function of these variables. Several specific examples are also given of currently used radiopharmaceutical products which can contain radioactive contaminants (I-123, In-111, Tl-201, Ir-191m, Rb-82, Au-195m). 7 references, 8 figures, 4 tables

  4. Mapping the radioactive contamination in urban environments after nuclear emergencies

    International Nuclear Information System (INIS)

    Kaiser, Jan Christian; Proehl, Gerhard; Woda, Clemens

    2008-01-01

    Full text: In the event of a nuclear emergency in an urban environment a reliable overview on the radioactive contamination is crucial for decision making. To assess the radiological situation both measurements of the gamma dose or dose rate (GDR) and results from urban dispersion and deposition models are used. Measurements may arrive from various sources like car-borne detectors or man-borne radiation-sensitive materials embedded in cell phones, flash memory devices or RFID chips. The measurements depend strongly on the detector environment. To account for this dependence each signal is multiplied by a location factor, which quantifies the deviation of the recorded signal from the hypothetical signal of a reference surface of infinitely extended lawn. Furthermore, the data originate from geo-referenced points or lines but do not provide full spatial information. We present here two approaches to produce maps of the reference GDR or surface contamination in urban areas, which are implemented in the Inhabited Areas Monitoring Module (IAMM) as part of the European decision support systems RODOS and ARGOS. Immediately after the accident, a few measurements are combined with the predictions of urban models using data assimilation. If enough measurements are available they are regionalised with geo-statistical interpolation algorithms like inverse distance weighting or kriging. Both approaches are demonstrated in hypothetical scenarios based on the explosion of a radioactive dispersion device. (author)

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

    Science.gov (United States)

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

    2017-04-01

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

  6. Methods for removing radioactive isotopes from contaminated streams

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  7. The Barents Sea, distribution and fate of radioactive contaminants

    International Nuclear Information System (INIS)

    Foeyn, L.; Heldal, H.E.; Svaeren, I.

    1999-01-01

    Possible contamination in the marine food webs of the Barents Sea may be a problem for a rational harvest of the area. Radioactive contamination has in this context a special public impact as even traces of radioactivity seems to be considered by the public to be a real danger. It is therefor of special importance, from a regulatory and fisheries point of view, to accumulate knowledge of the behaviour of radioactive elements in the marine ecosystems of the Barents Sea in order to place this contamination in proper and realistic proportions

  8. Process for reducing radioactive contamination in waste product gypsum

    International Nuclear Information System (INIS)

    Lange, P.H. Jr.

    1979-01-01

    A process is described for reducing the radioactive contamination in waste product gypsum in which waste product gypsum is reacted with a dilute sulfuric acid containing barium sulfate to form an acid slurry at an elevated temperature, the slurry is preferably cooled, the acid component is separated from the solid, and the resulting solid is separated into a fine fraction and a coarse fraction. The fine fraction predominates in barium sulfate and radioactive contamination. The coarse fraction predominates in a purified gypsum product of reduced radioactive contamination

  9. Assessment of low levels of radioactive contamination

    International Nuclear Information System (INIS)

    Gray, P.W.

    1988-01-01

    This report describes a general methodology for the verification and clearance of sites contaminated with radioactive materials; general expressions for the risk or health detriment are derived. Techniques are developed, using Bayesian decision theory, to optimize the resources allocated to a site monitoring procedure, and to construct the probability distribution of the spatial distribution of specific activity within a site. A technique is also developed to determine the probability that a localized source of specified characteristics will not be detected by the monitoring procedure employed. The application of these techniques is illustrated by means of simple examples. This report confirms that a very large number of measurements are needed if a source of localized activity is to be detected with a high probability, and demonstrates how prior information about past radiological practices might be used to increase the probability of detection. Proposals are made for a programme of research to determine whether or not representative sites can be verified using current measuring techniques. (author)

  10. Laser techniques for radioactive decontamination gives metallic surfaces

    International Nuclear Information System (INIS)

    Escobar Alracon, L.; Molina, G.; Vizuet Gonzalez, J.

    1998-01-01

    In this work it presented the prototype for system decontamination at diverse component with removable superficial contamination, using the technique gives laser ablation, for the evaporation at the pollutant. It discusses the principle in the fact that system, as well as the different elements that compose it. The are presented the obtained results when irradiating with a laser a surface without radioactive contamination to verify the system operation

  11. Radioactive standards and calibration methods for contamination monitoring instruments

    Energy Technology Data Exchange (ETDEWEB)

    Yoshida, Makoto [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-06-01

    Contamination monitoring in the facilities for handling unsealed radioactive materials is one of the most important procedures for radiation protection as well as radiation dose monitoring. For implementation of the proper contamination monitoring, radiation measuring instruments should not only be suitable to the purpose of monitoring, but also be well calibrated for the objective qualities of measurement. In the calibration of contamination monitoring instruments, quality reference activities need to be used. They are supplied in different such as extended sources, radioactive solutions or radioactive gases. These reference activities must be traceable to the national standards or equivalent standards. On the other hand, the appropriate calibration methods must be applied for each type of contamination monitoring instruments. In this paper, the concepts of calibration for contamination monitoring instruments, reference sources, determination methods of reference quantities and practical calibration methods of contamination monitoring instruments, including the procedures carried out in Japan Atomic Energy Research Institute and some relevant experimental data. (G.K.)

  12. Surface deposition from radioactive plumes

    International Nuclear Information System (INIS)

    Garland, J.A.

    1980-01-01

    Accidents involving nuclear plants may release radioactive particles and gases to the atmosphere. Dry deposition of particles has been investigated mainly in the laboratory and a general understanding of the transfer mechanisms has been established. However there is apparently a substantial discrepancy between the few field observations of dry deposition of particles and laboratory measurements, particularly for 0.1 - 1 μm particles for which laboratory work shows very small deposition rates. In addition there are few estimates of deposition rates for forest and some other kinds of terrain. The most important gas in the context of a nuclear accident is I-131 and the behaviour of this gas at grass surfaces has received much attention. However smaller quantities of other gases and vapours may be released and the surface absorption of these species may require further investigation. In addition there is little knowledge of the behaviour of gases over many types of surface. The rate of deposition of particles and gases is influenced by many parameters including wind speed and the temperature stratification of the lower atmosphere. Conditions which give poor atmospheric dispersion usually give lower deposition velocities. Transfer to man depends on the availability of deposited materials on crops and grass. A wide range of isotopes including iodine and several metallic fission products are lost with a half life for residence on grass ranging from a few days to a few tens days, depending on climatic conditions

  13. Theoretical investigation of aspects of radioactive contamination

    International Nuclear Information System (INIS)

    Smith, A.H.; Chandratillake, M.R.; Taylor, J.B.

    1998-01-01

    The BNFL programme of work has investigated theoretical aspects of the mechanisms responsible for the deposition and adherence of contamination to metallic surfaces and the energetics of physical decontamination processes. The work has been conducted in two phases: The theoretical and laboratory study of deposition of species from aqueous media on to stainless steel; Theoretical assessment of the forces causing the attraction of PuO 2 and UO 2 particles to stainless steel in an air environment and comparison of these forces with the energies delivered by physical jetting processes. The first phase produced a model which was found to give good agreement with plant operational experience of the deposition of simple aqueous ions such as Cobalt. Due to the complexities, however, of surface / colloid and surface / particle interactions the model was found not to be successful at predicting deposition for more complex compounds, such as Ruthenium Nitrosyls. At this stage the model had fulfilled its original requirement of underpinning design work on pipework shielding systems and it was decided not to pursue the library of chemical speciation data that would be necessary to model the behaviour of a full spectrum of possible contaminants. The second phase predicts by theoretical analysis that the relation of the energy delivered by jetting techniques to the physical forces causing the adherence of PuO 2 and UO 2 particles will vary considerably with particle size. This is particularly notably for larger PuO 2 particles which are firmly held as a result of high levels of electrostatic charge due to their intense alpha activity. Small particles tend to be difficult to remove due to the low profile that they present to the jetting medium. Large and small PuO 2 particles and small UO 2 particle are thus predicted to be difficult to remove and will present an energy threshold which may not be crossed by all decontamination techniques. (author)

  14. Method of melting decontamination of radioactive contaminated metals

    International Nuclear Information System (INIS)

    Uda, Tatsuhiko; Miura, Noboru; Tsuchiya, Hiroyuki.

    1984-01-01

    Purpose: To improve the transfer efficiency of radioactive materials into slags. Method: Contaminated metals are melt with adding slagging agent in order to transfer the radioactive materials into the slag, where the slagging agent holds less free energy than that of metal oxides contaminated with radioactive materials in order to promote the transfer of the contaminated materials into the slag layer. This effect can also be attained on metals or alloys other than iron contaminated with radioactive materials. In the case of alloy, the slagging agent is to containing such metal oxide that free energy is less than that of the oxide of metal being the main ingredient element of the alloy. The decontamination effect can further be improved by containing halogenide such as calcium fluoride together with the metal oxide into the slagging agent. (Ikeda, J.)

  15. Radioactive contamination of aquatic media and organisms; La contamination radioactive des milieux et des organismes aquatiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    After a brief account of the radioactive wastes produced by peaceful or military uses of Atomic Industry, the author first describes a series of observations carried out 'in the field' on the extent of contamination in aquatic organisms with respect to that of the medium. The experimental studies are then analysed, with reference both to the radioisotope metabolism and to the factors and types of contamination of aquatic organisms by wastes from atomic industry. A precise experimental project is presented at the end of the paper, including almost 300 references. (author) [French] Apres une courte etude des dechets radioactifs produits par les utilisations pacifiques ou militaires de l'Industrie Atomique, l'auteur fait etat d'abord des observations effectuees 'sur le terrain' concernant l'extension de la contamination des organismes aquatiques en rapport avec celle du milieu. L'auteur analyse ensuite les etudes experimentales se rapportant aussi bien au metabolisme des radioisotopes qu'aux facteurs et aux modalites de la contamination des organismes aquatiques par les dechets de l'industrie atomique. Un projet de travail experimental precis est presente a la fin de cette revue qui comporte pres de 300 references bibliographiques. (auteur)

  16. Radioactive contamination of aquatic media and organisms; La contamination radioactive des milieux et des organismes aquatiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    After a brief account of the radioactive wastes produced by peaceful or military uses of Atomic Industry, the author first describes a series of observations carried out 'in the field' on the extent of contamination in aquatic organisms with respect to that of the medium. The experimental studies are then analysed, with reference both to the radioisotope metabolism and to the factors and types of contamination of aquatic organisms by wastes from atomic industry. A precise experimental project is presented at the end of the paper, including almost 300 references. (author) [French] Apres une courte etude des dechets radioactifs produits par les utilisations pacifiques ou militaires de l'Industrie Atomique, l'auteur fait etat d'abord des observations effectuees 'sur le terrain' concernant l'extension de la contamination des organismes aquatiques en rapport avec celle du milieu. L'auteur analyse ensuite les etudes experimentales se rapportant aussi bien au metabolisme des radioisotopes qu'aux facteurs et aux modalites de la contamination des organismes aquatiques par les dechets de l'industrie atomique. Un projet de travail experimental precis est presente a la fin de cette revue qui comporte pres de 300 references bibliographiques. (auteur)

  17. Radioactive contamination of food and the intake by man

    International Nuclear Information System (INIS)

    Frissel, M.J.; Blaauboer, R.O.; Koester, H.W.; Leenhouts, H.P.; Stoutjesdijk, J.F.; Vaas, L.H.

    1989-01-01

    This paper describes the different pathways by which food is contaminated after a release of radionuclides into the environment. Equations to calculate the contamination level, as well as the most important parameters used in these equations, are included. Thereupon is explained how the radiation dose can be calculated from the intake of radioactivity. The principles which are used to derive criteria for the amounts of radioactivity which are allowed in food are described. (author)

  18. Redispersion of indoor surface contamination: a review

    International Nuclear Information System (INIS)

    Sansone, E.B.; Slein, M.W.

    1978-01-01

    The importance of surface contamination as a potential source of exposure to hazardous materials is discussed. Data from the literature concerning the resuspension of indoor surface contamination are presented. Reported procedures for quantitating surface contamination are compared. It is suggested that, despite its limitations, surface contamination monitoring may be useful in estimating potential risks from hazardous materials. (Auth.)

  19. Investigation of radioactive contamination at non-radioactive drains of the Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    Koide, Hiroaki; Imanaka, Tetsuji; Ebisawa, Toru; Kawano, Shinji; Kobayashi, Keiji.

    1982-05-01

    In April, 1981, it was disclosed that a drainage area at the Tsuruga Nuclear Power Station was so much contaminated with radioactivites. Although Ministry of International Trade and Industry (MITI) officially provided an explanation of a process that resulted in the contamination, many problems remain unsolved on account of insufficient and limited investigations. The authors collected mud samples from contaminated manholes and examined radioactivities in them through the measurement of #betta#- and #betta#-spectra. Chemical separation of the samples was carried out in order to obtain precise concentration of radioactive cesium. Results are as follows: i) the concentration of radioactivities does not show monotonous decrease along the stream line but an anomalous peak at downstream manholes, ii) at the manhole specified No. 6 located rather downstream, 137 Cs concentration is significantly high and the composition of radioactive nuclides is quite different from that in the other manholes, and iii) additional radioactive contamination was observed in other manholes of non-radioactive drains which would not be influenced by the accident explained by MITI. Our present work has provided much more data than by MITI and made it clear that the overall data cnnot be consistent with the simple MITI explanation; a single radioactive release accident caused the disclosed contamination. It is concluded that non-radioactive water drains at the Tsuruga Nuclear Power Station had been under continual contamination. (author)

  20. Economics and risks of recycling radioactively contaminated concrete

    International Nuclear Information System (INIS)

    Parker, F.L.; Ayers, K.W.

    1997-01-01

    As Decontamination and Decommissioning activities proceed within the DOE complex, tremendous volumes of both radioactively contaminated and non-contaminated concrete will be processed for disposal. Current practice is to decontaminate the concrete, dispose of the contamination at LLW facilities and ship the concrete rubble to C ampersand D landfills for disposal. This study evaluates the economic, health and safety, legal, and social aspects of recycling radioactively contaminated concrete. Probabilistic models were used to estimate costs and risks. The model indicates that the radioactively contaminated concrete can be recycled at the same or lower cost than current or alternative practices. The risks associated with recycling were consistently less than or equal to the other alternatives considered

  1. Radioactive waste management for a radiologically contaminated hospitalized patient

    International Nuclear Information System (INIS)

    Pina Jomir, G.; Michel, X.; Lecompte, Y.; Chianea, N.; Cazoulat, A.

    2015-01-01

    Radioactive waste management in the post-accidental phase following caring for a radiologically contaminated patient in a hospital decontamination facility must be anticipated at a local level to be truly efficient, as the volume of waste could be substantial. This management must comply with the principles set out for radioactive as well as medical waste. The first step involves identification of radiologically contaminated waste based on radioactivity measurement for volume reduction. Then, the management depends on the longest radioactive half-life of contaminative radionuclides. For a half-life inferior to 100 days, wastes are stored for their radioactivity to decay for at least 10 periods before disposal like conventional medical waste. Long-lived radioactive waste management implies treatment of liquid waste and special handling for sorting and packaging before final elimination at the French National Agency for Radioactive Waste Management (ANDRA). Following this, highly specialized waste management skills, financial responsibility issues and detention of non-medical radioactive sources are questions raised by hospital radioactive waste management in the post-accidental phase. (authors)

  2. Control of radioactive contamination of food in the country Somogy

    International Nuclear Information System (INIS)

    Varga, E.; Viragh, I.

    1980-01-01

    The radioactive contamination of spinach, sorrel, lettuce, animal bones, milk and fish was determined in the period 1961-1978. Peak values were measured in 1963 and 1976. The contamination of plants reached higher levels, however, it did not exceed 25 pCi per g dry weight. (L.E.)

  3. Radioactive contamination in Arctic - present situation and future challenges

    International Nuclear Information System (INIS)

    Strand, Per

    2002-01-01

    There is currently a focus on radioactivity and the Arctic region. The reason for this is probably the high number of nuclear sources in parts of the Arctic and the vulnerability of Arctic systems to radioactive contamination. The Arctic environment is also perceived as a wilderness and the need for the protection of this wilderness against contamination is great. In the last decade information has also been released concerning the nuclear situation which has caused concern in many countries. Due to such concerns, the International Arctic Environmental Protection Strategy (IAEPS) was launched in 1991 and the Arctic Monitoring and Assessment Programme (AMAP) was established. AMAP is undertaking an assessment of the radioactive contamination of the Arctic and its radiological consequences. In 1996 IAEPS became part of the Arctic Council. AMAP presented one main report in 1997 and another in 1998. There are also several other national, bilateral and international programmes in existence which deal with this issue. This paper summarises some of current knowledge about sources of radioactive contamination, vulnerability, exposure of man, and potential sources for radioactive contamination within Arctic and some views on the future needs for work concerning radioactivity in Arctic. (au)

  4. In-situ vitrification of radioactively contaminated soils: summary paper

    International Nuclear Information System (INIS)

    Buelt, J.L.; Fitzpatrick, V.F.

    1987-01-01

    The in-situ vitrification (ISV) process is a new technology that has been developed from its conceptual phase through selected field-scale application tests during the last six years. In situ vitrification converts contaminated soils and waste inclusions into a durable glass and crystalline waste form by in-place melting. Electrodes are inserted into the soil to be treated and an electrical current is passed through the soil to be treated and an electrical current is passed through the soil to melt it. After cooling, the process fixes (TRU) and fission product radionuclides making them relatively nonleachable, resistant to intrusion, and nondispersible when intentionally disturbed. Another application considered for isolation of radioactively contaminated soils, but not yet developed, is the generation of impermeable barrier walls to prevent ground water seepage into a site. The barrier technique could also be used over the surface of an existing disposal site to deter plant and animal intrusion. The development units have been extensively tested with many types of soils and waste inclusions such as concrete, buried metals, sealed containers, organic chemicals with high boiling points such as polychlorinated biphenyls, and inorganic chemicals, including toxic heavy metals, nitrates, and sulfates. Nitrates and organics are destroyed, while heavy metals and fluorides are retained to a high percentage within the molten soil during processing. At $200 to $300/m 3 for radioactive waste, the process is economically competitive with many alternative remediation processes. The ISV process has been developed to the point where it is ready for large-scale field testing at an actual TRU-contaminated soil site. 5 references, 2 figures, 2 tables

  5. Control System Radioactive Contamination in Food Samples in Poland

    International Nuclear Information System (INIS)

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

    2001-01-01

    Full text: The analyses of the level of radioactive contamination in food samples are carried out by the Service for Measurements of Radioactive Contamination (SMRC) in Poland. The Service was brought into existence in 1961. The Service comprises of a network of measurement stations and the Centre of Radioactive Contamination Measurements (CRCM). The duty of the Centre is being executed by the Central Laboratory for Radiological Protection (CLRP). The uniform methods of sampling are used in measurement stations. All important foodstuff: milk, meat, vegetables, fruit, cereals are controlled in the Service stations. The radiochemical and spectrometric methods are used to determine the activity of radioactive isotopes. The standard equipment of the measurement station is the measurement system type SAPOS-90 and multichannel analyser with scintillation or germanium detector. The structure of the Service, kinds of samples tested by each station, program of sampling in normal and during accident situation are presented in this paper. (author)

  6. Characterization and remediation of highly radioactive contaminated soil at Hanford

    International Nuclear Information System (INIS)

    Buckmaster, M.A.; Erickson, J.K.

    1993-09-01

    The Hanford Site, Richland, Washington, contains over 1,500 identified waste sites and numerous groundwater plumes that will be characterized and remediated over the next 30 years. As a result of the Hanford Federal Facility Agreement and Consent Order, the US Department of Energy (DOE) has initiated a remedial investigation/feasibility study (RI/FS) at the 200-BP-1 operable unit. The 200-BP-1 RI/FS is the first Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) investigation on the Hanford Site that involves highly radioactive and chemically contaminated soils. The initial phase of site characterization was designed to assess the nature and extent of contamination associated with the source waste sites within the 200-BP-1 operable unit. Characterization activities consisted of drilling and sampling, chemical and physical analysis of samples, and development of a conceptual vadose zone model. These data were then used. to develop remedial alternatives during the FS evaluation. The preferred alternative resulting from the RI/FS process for the 200-BP-1 operable unit is to construct a surface isolation barrier. The multi-layered earthen barrier will be designed to prevent migration of contaminants resulting from water infiltration, biointrusion, and wind and water erosion

  7. Auburn Steel Company radioactive contamination incident

    International Nuclear Information System (INIS)

    Bradley, F.J.; Cabasino, L.; Kelly, R.; Awai, A.; Kasyk, G.

    1986-04-01

    On February 21, 1983, workers at the Auburn Steel Company, Auburn, New York discovered that about 120 tons of steel poured that day had become contaminated with 60 Co. In addition to the steel, the air cleaning system and portions of the mill used in casting the steel were contaminated. Approximately 25 curies of 60 Co were involved. Decontamination and disposal of the contamination cost in excess of $2,200,000. This report details the discovery of the contamination, decontamination of the plant and disposal of the contamination

  8. Method of burning ion-exchange resin contaminated with radioactivity

    International Nuclear Information System (INIS)

    Suzuki, Shigenori.

    1986-01-01

    Purpose: To process spent ion exchange resins to reduce their volume, without increasing the load on a off-gas system and in a stable state and at the same time not leaving any uncombusted portions. Method: The water slurries of the ion exchange resins contaminated with radioactive materials is dehydrated or dry combusted to reduce the water content. A binder is then added to solidify the ion exchange resin. The solidified ion exchange resins are then combusted in a furnace. This prevents the ion exchange resin from being dispersed by air and combustion gases. Furthermore, the solidified ion exchange resins in the form of small pellets burn from the surface inwards. Moreover the binder is carbonized by the combustion heat and promotes combustion to convert the ion exchange resins into a solid mass, making sure that no uncombusted portion is left. (Takahashi, M.)

  9. Some problems of risk assessment in cases of environmental radioactive and chemical contamination in regions of the Ural radioactive trail

    International Nuclear Information System (INIS)

    Kryshev, I.I.; Isaeva, L.N.; Sazykina, T.G.

    1995-01-01

    A methodology of risk assessment if being developed to permit the analysis of possible consequences of radioactive and chemical environment contamination on the territory of the Urals radioactive trail. The assessment of hazards from radioactive contamination of the Techa river (Muslyumovo) has been carried out. A comparison of radioactive and chemical risks for the population of Kasli has been made

  10. The radioactive contamination level in Croatia by means of radioactive rainwaters, caused by the accident in NPP 'Lenin'

    International Nuclear Information System (INIS)

    Barishicj, D.; Koshuticj, K.; Kvastek, K.; Lulicj, S.; Tuta, J.; Vertachnik, A.; Vrhovac, A.

    1987-01-01

    In this paper, the radioactive contamination level in Croatia by means of radioactive rainwaters, caused by the accident in NPP 'Lenin', has been described. The results represent the sum of measured and evaluated data, the map of the radioactive contamination in Croatia caused by radioactive rainwaters between April, 28 to May, 20 1986 has been constructed. (author) 3 tabs.; 5 figs

  11. Experiences in monitoring airborne radioactive contamination in JAERI

    International Nuclear Information System (INIS)

    Ikezawa, Y.; Okamoto, T.; Yabe, A.

    1980-01-01

    The following results were obtained at the Japan Atomic Energy Research Institute (JAERI) from experience in air monitoring at the hot cells for handling highly radioactive materials, the glove box containing plutonium and the cell for producing 99 Mo. (1) The ratios of activities of airborne dust to those of whole dust were of the order of 10 -2 for the semi-volatile form of 125 Sb, and 10 -3 to 10 -4 for the particulate form of 137 Cs, 144 Ce and 144 Pr, when irradiated fuels were cut in the hot cells. (2) The activity median aerodynamic diameter (AMAD) of airborne particle size distributions varied from O.4 to 15 μm with changing geometric standard deviation (sigmasub(g)) 1.7 to 7, depending on types of metallurgical treatment of fuels and on kinds of work in the cells. (3) A resuspension factor (the ratio of the concentration of airborne contamination to the surface contamination) was found to be 4x10 -8 to approximately 2x10 -7 cm -1 for plutonium oxide deposited on the floor surface. (4) The collection efficiency of the charcoal-loaded filter paper for airborne radioiodine, consisting of 60% inorganic and 40% organic iodide, was over 95% under conditions of relative humidity 40 to approximately 80% and face velocity 50 cm/sec, during the production of 99 Mo. (H.K.)

  12. Water in the March river radioactively contaminated

    International Nuclear Information System (INIS)

    Englander, A.G.

    1990-01-01

    A curve of the tritium contamination of the March river measured in Austria from 1976 to 1989 is shown. The conjecture is put forward that this contamination is caused by the Dukovani power plant in the neighbouring CSFR. Further measurements are called for

  13. Optical measurements on contaminated surfaces

    Science.gov (United States)

    Bonham, T. E.; Schmitt, R. J.; Linford, R. M. F.

    1975-01-01

    A bidirectional reflectometer system was developed for in situ measurements of the changes in spectral reflectance of surfaces contaminated with films of organic materials. The system permits experiments with films of controlled thickness in an environment that simulates the thermal, radiation, and vacuum conditions of space. The mechanical and optical construction of the reflectometer are discussed in detail, and actual data curves are used to illustrate its operation and performance.

  14. Radioactive contamination characteristics in China following Chernobyl accident

    International Nuclear Information System (INIS)

    Wang Zuoyuan

    1987-01-01

    In the aftermath of Chernobyl nuclear reactor accident, the Environmental Radiation Surveillance Network of Ministry of Public Health of China has done monitoring on environmental samples to determine the contamination levels of radioactivity. Radionuclides, such as I-131, I-132, Cs-137, Cs-134 and Te-132, were found on surface of airplanes, which flew in domestic airlines between May 1-3, that means the radionuclides from Chernobyl accident already reached high altitude atmosphere over China, but the concentration was much lower than that in Europe. During the period of May 2-15, in most stations, radionuclides were found in different environmental samples, such as air, milk, vegetables, rain water, river and lake water, and sheep thyroid. Radioactivity levels of samples were higher in north part of China than in south. The amounts of radionuclides in all samples were well below the derived air concentrations and derived intake concentrations specified in the National Basic Health Standards for Radiological Protection. Thus, the public need not to take any precautions for the purpose of radiation protection

  15. Radioactive elements found in plants contaminated by radioactive rain

    Energy Technology Data Exchange (ETDEWEB)

    Tanidazawa, M; Ishihara, T

    1954-01-01

    Ashes obtained from contaminated trifolium repens, astragalus sinicus, and rumex japonicus were studied. The precipitate obtained by treating the acidic solution of the ash with H/sub 2/S followed by Fe/sup + +/ in the presence of NH/sub 3/ and NH/sub 4/Cl contained Y, Sr, and the rare earth elements.

  16. The total amounts of radioactively contaminated materials in forests in Fukushima, Japan

    Science.gov (United States)

    Hashimoto, Shoji; Ugawa, Shin; Nanko, Kazuki; Shichi, Koji

    2012-01-01

    There has been leakage of radioactive materials from the Fukushima Daiichi Nuclear Power Plant. A heavily contaminated area (≥ 134, 137Cs 1000 kBq m−2) has been identified in the area northwest of the plant. The majority of the land in the contaminated area is forest. Here we report the amounts of biomass, litter (small organic matter on the surface of the soil), coarse woody litter, and soil in the contaminated forest area. The estimated overall volume and weight were 33 Mm3 (branches, leaves, litter, and coarse woody litter are not included) and 21 Tg (dry matter), respectively. Our results suggest that removing litter is an efficient method of decontamination. However, litter is being continuously decomposed, and contaminated leaves will continue to fall on the soil surface for several years; hence, the litter should be removed promptly but continuously before more radioactive elements are transferred into the soil. PMID:22639724

  17. Development of plastic scintillator based food radioactivity contamination monitoring system

    International Nuclear Information System (INIS)

    Parihar, A.; Sahani, R.M.; Mahala, V.K.; Vaijapurkar, S.G.

    2016-01-01

    Radioactivity is naturally present in soil, water and food stuffs. Food can be contaminated after discharge of radioactivity into the environment from industries that concentrate natural radionuclide and from civil or military nuclear operations. The contamination can be in three ways; by direct deposition, through the food chain and induced radioactivity due to exposure of high neutron flux. The health effects on human depend on the type of radionuclide and the length of time people are exposed to it. The studies of fission product behaviour in the food chain have revealed radionuclide Strontium-90, Caesium 137 and Iodine-131 are of major concern. Plastic scintillator is already developed indigenously at Defence Laboratory, Jodhpur. Efforts has been made to develop a portable field instrument using plastic scintillator for assessment of beta ( 90 Sr) and gamma ( 137 Cs and 131 I) radioactivity in food

  18. Investigation to radioactive contamination of pool water in IMEF

    International Nuclear Information System (INIS)

    Song, Ung Sup; Jung, Yang Hong; Lee, J. H.; Lee, H. K.

    2003-06-01

    The pool (3x6x10) in irradiated materials examination facility is usually used for the purpose of taking the specimen out of cask loaded into the pool, and carrying in/out the specimen to/ from the hot cell. Always, it must be cared for the water into the pool to be fine condition because all operation are worked with the naked eye during taking an irradiated materials out of the cask and plunging them in the bucket-elevator. In the aspects of the radioactive remained substances in the water must be controlled so that the amount of substances to be lower than the standard amount prescribed by RCA Korea Activity in a part of radioactive contamination control. In consequence, an expertness of status and a practical use of skill make possible the prevention of radioactive material's diffusion or the radioactive contamination of pool water and safety work

  19. Method of melt-decontaminating alumium contaminated with radioactivity

    International Nuclear Information System (INIS)

    Uda, Tatsuhiko; Iba, Hajime; Miura, Noboru; Kawasaki, Katsuo.

    1986-01-01

    Purpose: To enable optimum deontamination for radioactive-contaminated aluminum by further improving the decontaminating effect of the slag agent added to radioactive contaminated materials. Method: The slag agent is mainly composed of chloride type slags having a high reactivity for mainly incorporating uranium compounds and easily reacting near the melting point of aluminum and incorporated with fluorides for weakening the deliquescent characteristic to the chloride materials. Further, those slag agents are selected which can be treated at a low temperature in order to prevent the uranium compounds once incorporated into the slags from re-melting into the molten aluminum. Typically, a slag agent comprising 14 LiF, 76 KCl - 10 BaCl 2 is preferred. The basicity of the slag agent ranges from 0.5 to 2 and the melting point is 700 deg C. The melting decontaminating efficiency for the radioactive-contaminated aluminum can thus be improved. (Horiuchi, T.)

  20. Chernobyl three years later: radiobiologic evaluation of a radioactive contamination

    International Nuclear Information System (INIS)

    Behar, A.; Cohen-Boulakia, F.; Othmani, S.

    1990-01-01

    On April 26, 1986, after partial fusion and confining loss by explosion of a nuclear reactor, 5 x 10(7) Ci of radionuclides escaped from Chernobyl. Three years later, maps show contamination by radioactive isotopes (formed during that period) of 21,000 km2 of Soviet soil, mainly in Byelorussia and part of the Ukraine. Decontamination measures have not been effective to date and 135,000 persons are being followed medically, taking into account the radioactive doses they received. An initial excess of morbidity from solid tumors has been noted much sooner than in the case of Hiroshima and Nagasaki, but its significance is in dispute. Three years later, only the extent of the ecologic disaster caused by the radioactive contamination can be confirmed. It is too early to draw conclusions about radiation-induced carcinogenesis for the contaminated population

  1. Design and development of food radioactivity contamination monitoring system

    International Nuclear Information System (INIS)

    Narayan, Pradeep; Vaijapurkar, S.G.; Bohra, Dinesh

    2014-01-01

    Radioactivity has been part and parcel of living being since the existence of the earth. It is available everywhere in our environment and being responsible for evolution of life on earth at some extent. However, the radioactivity in excess of the natural radioactive can have harmful effects on living being. The radiation exposure can be of external or internal origin or of both. The main route of internal radiation exposure is through the contaminated food chains. The concentration of natural radioactivity in food varies in range of 40-600 Bq/kg. 40 K being the single major radionuclide of food with typical radioactivity; 50 Bq/kg in milk, 420 Bq/kg in milk powder, 165 Bq/kg in potatoes, and 125 Bq/kg in beef is also the main contributor of natural radiation doses to human being. Measurement of radioactivity in food items and drinks is thus very important in controlling the internal exposure to human being especially in case of nuclear disaster. Though, the methods and techniques for food radioactivity measurement already existing, the need of portable instrument is warranted to measure the radioactivity in food items in raw form. Measurement of radioactivity may help in quick and mass screening of food items in case of nuclear emergencies. Any enhanced level of radioactivity in food items especially in case of nuclear emergency need to be evaluated for controlling its spread and restriction of consumption by the public. This way, it may help in managing internal radioactivity contamination to human being

  2. Dosimetric system for measurement of radioactive contaminations

    International Nuclear Information System (INIS)

    Litynski, Z.; Pienkos, J.P.; Witkowski, J.; Zadrozny, S.

    1985-01-01

    A dosimetric system for personnel dosimetry and monitoring measuring a contamination without time delay and dead time is described. The system ensures many-point measurement and minimalization of background radiation influence. 1 fig. (A.S.)

  3. Laser Decontamination of Surfaces Contaminated with Cs+ Ion

    International Nuclear Information System (INIS)

    Baigalmaaa, B.; Won, H. J.; Moon, J. K.; Jung, C. H.; Lee, K. W.; Hyun, J. H.

    2008-01-01

    Laser decontamination technology has been proven to be an efficient method for a surface modification of metals and concretes contaminated with radioactive isotopes. Furthermore, the generation of a secondary waste is negligible. The radioactivity of hot cells in the DFDF (Dupic Fuel Development Facility) is presumed to be very high and the predominant radionuclide is Cs-137. A series of laser decontamination studies by a fabricated Q-switched Nd:YAG laser system were performed on stainless steel specimens artificially contaminated with Cs+ ion. Decontamination characteristics of the stainless steel were analyzed by SEM and EPMA

  4. Radioactive contamination in metal recycling industry - an environmental issue

    International Nuclear Information System (INIS)

    Agarwal, S.P.

    2012-01-01

    Metal recycling has become an important industrial activity worldwide; it is seen as being socially and environmentally beneficial because it conserves natural ore resources and saves energy. However, there have been several accidents over the past decades involving orphan radioactive sources or other radioactive material that were inadvertently collected as metal scrap that was destined for recycling. The consequences of these accidents have been serious with regard to the protection of people and the environment from the harmful effects of ionizing radiation as well as from an economic point of view. India produces and exports steel products to various countries. In the recent years there were rejection and return of steel products as they were found to be contaminated with trace quantities of radioactive materials. During investigation of incidents of radioactive contamination in steel products exported from India, it was observed that steel products are contaminated with low level radioactivity. Though radioactivity level in steel products is found to be too low to pose any significant hazards to the handling personnel or to the users or the public at large, its presence is undesirable and need to be probed as to how it has entered in the steel products. Atomic Energy Regulatory Board (AERB) has investigated the incidents of such nature in the recent past and it is gathered that the steel products are made out of steel produced in a foundry where metal scrap containing radioactive material has been used. In this talk, incidents of radioactive contamination, its roots cause, and its radiological impact on person, property and environment, lessons learnt, remedial measures and international concerns will be discussed

  5. Hydrogen Contamination of Niobium Surfaces

    International Nuclear Information System (INIS)

    Viet Nguyen-Tuong; Lawrence Doolittle

    1993-01-01

    The presence of hydrogen is blamed for dramatic reductions in cavity Q's. Hydrogen concentration is difficult to measure, so there is a great deal of Fear, Uncertainty, and Doubt (FUD) associated with the problem. This paper presents measurements of hydrogen concentration depth profiles, commenting on the pitfalls of the methods used and exploring how material handling can change the amount of hydrogen in pieces of niobium. Hydrogen analysis was performed by a forward scattering experiment with Helium used as the primary beam. This technique is variously known as FRES (Forward Recoil Elastic Scattering), FRS, HFS (Hydrogen Forward Scattering), and HRA (Hydrogen Recoil Analysis). Some measurements were also made using SIMS (Secondary Ion Mass Spectrometry). Both HFS and SIMS are capable of measuring a depth profile of Hydrogen. The primary difficulty in interpreting the results from these techniques is the presence of a surface peak which is due (at least in part) to contamination with either water or hydrocarbons. With HFS, the depth resolution is about 30 nm, and the maximum depth profiled is about 300 nm. (This 10-1 ratio is unusually low for ion beam techniques, and is a consequence of the compromises that must be made in the geometry of the experiment, surface roughness, and energy straggling in the absorber foil that must be used to filter out the forward scattered helium.) All the observed HFS spectra include a surface peak which includes both surface contamination and any real hydrogen uptake by the niobium surface. Some contamination occurs during the analysis. The vacuum in the analysis chamber is typically a few times 10(sup -6) torr, and some of the contamination is in the form of hydrocarbons from the pumping system. Hydrocarbons normally form a very thin (less than a monolayer) film which is in equilibrium between arrival rate and the evaporation rate. In the presence of the incoming ion beam, however, these hydrocarbons crack on the surface into non

  6. Assessment of sites concerning radioactive contamination during preparation of a Contamination Site Register

    International Nuclear Information System (INIS)

    Gellermann, Rainer; Flesch, Klaus

    2014-01-01

    Experience gained since 1990 in the new, but also old German Federal States has shown that there are radioactive contaminated sites beside the legacies of uranium mining in Germany which caused exposures exceeding the radiation protection limits for members of the public. The reason for this situation is that radioactivity has been excluded in the compilation of the register for potentially hazardous sites that are prepared routinely in the context of soil protection assessments. Moreover, the information contained in these registers is not yet evaluated regarding aspects of radioactivity. In many cases, the information existing at the soil protection authorities needs only to be additionally filtered in order to identify potentially hazardous sites for radioactive contamination. For that reason, the working group ''Natural radioactivity'' (AKNAT) of the German-Swiss Radiation Protection Association developed a specific catalogue of business branches that provides indications for radioactive legacies.

  7. Method of melting and decontaminating radioactive contaminated aluminum material

    International Nuclear Information System (INIS)

    Uda, Tatsuhiko; Miura, Noboru; Kawasaki, Katsuo; Iba, Hajime.

    1986-01-01

    Purpose: To improve the decontaminating efficiency upon melting decontamination of radioactive-contaminated aluminum materials. Method: This invention concerns an improvement for the method of melting decontamination by adding slug agent composed of organic compound to contaminated aluminum material and extracting the radioactive materials into the slug thereby decontaminating the aluminum material. Specifically metals effective for reducing the active amount of aluminum are added such that the content is greater than a predetermined value in the heat melting process. The metal comprises Mg, Cu or a mixture thereof and the content is more than 4 % including those previously contained in the aluminum material. (Ikeda, J.)

  8. Radioactive contamination of the biosphere and consequences for food supply

    International Nuclear Information System (INIS)

    Wiechen, A.

    1989-01-01

    The paper deals with all aspects of radioactive contamination of the biosphere and corresponding consequences for food supply. In particular, releases of radioactivity by nuclear weapon tests in the early 60's and nuclear accidents in recent years are discussed. Contamination of food in the Federal Republic of Germany by these events and corresponding ingestion dose are demonstrated using examples. Furthermore diffusion of radionuclides and their transfer through the food chains to man are described. Suitable methods of decontamination at different production steps and their viability are discussed. (orig.) [de

  9. Radioactive contamination of workers. General recommendation and procedures

    International Nuclear Information System (INIS)

    Mastro, N.L. del; Santos, O.R. dos; Silva, E.N.D.; Santos, A.J. dos.

    1987-09-01

    The present publication has an objective to provide data and information to be used by workers who handle with or eventually could enter in touch with radioactives substances. The authors have made a compilation of subjects got from the literature on several aspects about radiocontamination, physical and chemical characteristics of radioisotopes, main sources of radioactive contamination, biological basis and treatement of internal and external decontamination. Special attention was paid to iodine and actinides contamination, particularly to uranium and plutonium. The conclusion are presented as general recommendation and synoptic tables. (Author) [pt

  10. Experimental study on source efficiencies for estimating surface contamination level

    International Nuclear Information System (INIS)

    Ichiji, Takeshi; Ogino, Haruyuki

    2008-01-01

    Source efficiency was measured experimentally for various materials, such as metals, nonmetals, flooring materials, sheet materials and other materials, contaminated by alpha and beta emitter radioactive nuclides. Five nuclides, 147 Pm, 60 Co, 137 Cs, 204 Tl and 90 Sr- 90 Y, were used as the beta emitters, and one nuclide 241 Am was used as the alpha emitter. The test samples were prepared by placing drops of the radioactive standardized solutions uniformly on the various materials using an automatic quantitative dispenser system from Musashi Engineering, Inc. After placing drops of the radioactive standardized solutions, the test materials were allowed to dry for more than 12 hours in a draft chamber with a hood. The radioactivity of each test material was about 30 Bq. Beta rays or alpha rays from the test materials were measured with a 2-pi gas flow proportional counter from Aloka Co., Ltd. The source efficiencies of the metals, nonmetals and sheet materials were higher than 0.5 in the case of contamination by the 137 Cs, 204 Tl and 90 Sr- 90 Y radioactive standardized solutions, higher than 0.4 in the case of contamination by the 60 Co radioactive standardized solution, and higher than 0.25 in the case of contamination by the alpha emitter the 241 Am radioactive standardized solution. These values were higher than those given in Japanese Industrial Standards (JIS) documents. In contrast, the source efficiencies of some permeable materials were lower than those given in JIS documents, because source efficiency varies depending on whether the materials or radioactive sources are wet or dry. This study provides basic data on source efficiency, which is useful for estimating the surface contamination level of materials. (author)

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

    Science.gov (United States)

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

    2017-11-01

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

  12. Transfer of radioactive contamination from milk to commercial dairy products

    International Nuclear Information System (INIS)

    Wilson, L.G.; Sutton, P.M.

    1988-01-01

    The fate of radioactive contamination resulting from fallout from the Chernobyl accident was studied during milk processing. A range of commercial dairy products was produced on a pilot-laboratory scale and the radiocaesium contents were measured by high-resolution gamma spectrometry. The results show that the radiocaesium partitioned with the water phase and therefore butter, cream and cheese had relatively low levels of radioactivity. Ion exchange demineralization was effective in removing radiocaesium from whey. Ultrafiltration of whey resulted in a reduction of radioactivity relative to retentate solids. (author)

  13. Early-stage bioassay for monitoring radioactive contamination in living livestock.

    Science.gov (United States)

    Yamaguchi, Toshiro; Sawano, Kaita; Kishimoto, Miori; Furuhama, Kazuhisa; Yamada, Kazutaka

    2012-12-01

    Soil samples from the ground surface and feces and blood from a mixed-breed male pig were collected on April 10, 2011 at a farm within 20 km of the Fukushima Daiichi nuclear power plant. The radioactivity of each sample was measured using a Ge semiconductor detector. Despite the fact that the pig had been fed non-contaminated imported feed, (131)I, (134)Cs and (137)Cs were detected in the feces, and (134)Cs and (137)Cs were detected in the blood clots. Because it is considerably difficult to measure radioactive contamination in the edible muscle of living livestock, bioassays are an option for the screening of radioactive contamination in living livestock to ensure food safety.

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  15. Some problems in calibrating surface contamination meters

    International Nuclear Information System (INIS)

    Chen Zigen; LI Xingyuan; Shuai Xiaoping.

    1984-01-01

    It is necessary that instruments are calibrated accurately in order to obtain reliable survey data of surface contamination. Some problems in calibrating surface contamination meters are expounded in this paper. Measurement comparison for beta surface contamination meters is organized within limited scope, thus survey quality is understood, questions are discovered, significance of calibration is expounded further. (Author)

  16. Test and evaluation of radioactively contaminated transducers and transmitters

    International Nuclear Information System (INIS)

    Strahm, R.C.

    1983-01-01

    People in the nuclear industries face some unique problems when handling, testing, or examining transducers and transmitters that have been radioactively contaminated. Although many people and organizations, including EG and G Idaho, have performed such work for many years, there are no set, structured approaches or procedures. This paper discusses a disciplined laboratory approach to contaminated transducer testing and evaluation, utilizing equipment and facilities developed specifically for this type of work

  17. The role of bioindicators in assessing radioactive contamination

    International Nuclear Information System (INIS)

    Marovicj, G.

    1990-01-01

    The paper is a survey of investigations into radioactive contamination of selected plant and animal species (bioindicators) which have the capacitr for multiple accumulation of fission products. Literature data on the contamination of bioindicators are compared with special reference to the accumulation of 131 I, 137 Cs and 90 Sr as a result of atmospheric nuclear experiments and the nuclear accident at Chernobyl. (author) 52 refs.; 3 figs [sh

  18. Rapid Evaluation of Radioactive Contamination in Rare Earth Mine Mining

    Science.gov (United States)

    Wang, N.

    2017-12-01

    In order to estimate the current levels of environmental radioactivity in Bayan Obo rare earth mine and to study the rapid evaluation methods of radioactivity contamination in the rare earth mine, the surveys of the in-situ gamma-ray spectrometry and gamma dose rate measurement were carried out around the mining area and living area. The in-situ gamma-ray spectrometer was composed of a scintillation detector of NaI(Tl) (Φ75mm×75mm) and a multichannel analyzer. Our survey results in Bayan Obo Mine display: (1) Thorium-232 is the radioactive contamination source of this region, and uranium-238 and potassium - 40 is at the background level. (2) The average content of thorium-232 in the slag of the tailings dam in Bayan Obo is as high as 276 mg/kg, which is 37 times as the global average value of thorium content. (3) We found that the thorium-232 content in the soil in the living area near the mining is higher than that in the local soil in Guyang County. The average thorium-232 concentrations in the mining areas of the Bayan Obo Mine and the living areas of the Bayan Obo Town were 18.7±7.5 and 26.2±9.1 mg/kg, respectively. (4) It was observed that thorium-232 was abnormal distributed in the contaminated area near the tailings dam. Our preliminary research results show that the in-situ gamma-ray spectrometry is an effective approach of fast evaluating rare earths radioactive pollution, not only can the scene to determine the types of radioactive contamination source, but also to measure the radioactivity concentration of thorium and uranium in soil. The environmental radioactive evaluation of rare earth ore and tailings dam in open-pit mining is also needed. The research was supported by National Natural Science Foundation of China (No. 41674111).

  19. Radioactivity of some alpha, beta and gamma emitting radionuclides in surface marine sediments of different bays in Algeria

    International Nuclear Information System (INIS)

    Noureddine, A.; Baggoura, B.

    1999-01-01

    Samples of surface (0-15) cm marine sediments of different grain sizes, namely sand, muddy and fine sand, were collected in the western, central and east coast of Algeria, to measure concentrations of natural and artificial radioactivity. The aim of this study is to detect any radioactive contamination, its origin and also to determine the uptake of radioactivity by marine surface sediments

  20. Measurement of Radioactive Contamination on Work Clothing of Workers Engaged in Decontamination Operations

    Science.gov (United States)

    Tsujimura, Norio; Yoshida, Tadayoshi; Hoshi, Katsuya

    To rationally judge the necessity of the contamination screening measurements required in the decontamination work regulations, a field study of the surface contamination density on the clothing of the workers engaged in decontamination operations was performed. The clothing and footwear of 20 workers was analyzed by high-purity germanium (HPGe) gamma-ray spectroscopy. The maximum radiocesium activities (134Cs + 137Cs) observed were 3600, 1300, and 2100 Bq for the work clothing, gloves, and boots, respectively, and the derived surface contamination densities were below the regulatory limit of 40 Bq/cm2. The results of this field study suggest that the upper bounds of the surface contamination density on the work clothing, gloves, and boots are predictable from the maximum soil loading density on the surface of clothing and footwear and the radioactivity concentration in soil at the site.

  1. Measurement of radioactive contamination on work clothing of workers engaged in decontamination operations

    International Nuclear Information System (INIS)

    Tsujimura, Norio; Yoshida, Tadayoshi; Hoshi, Katsuya

    2016-01-01

    To rationally judge the necessity of the contamination screening measurements required in the decontamination work regulations, a field study of the surface contamination density on the clothing of the workers engaged in decontamination operations was performed. The clothing and footwear of 20 workers was analyzed by high-purity germanium (HPGe) gamma-ray spectroscopy. The maximum radiocesium activities ("1"3"4Cs + "1"3"7Cs) observed were 3600, 1300, and 2100 Bq for the work clothing, gloves, and boots, respectively, and the derived surface contamination densities were below the regulatory limit of 40 Bq/cm"2. The results of this field study suggest that the upper bounds of the surface contamination density on the work clothing, gloves, and boots are predictable from the maximum soil loading density on the surface of clothing and footwear and the radioactivity concentration in soil at the site. (author)

  2. Biological effects of water reservoir radioactive contamination

    International Nuclear Information System (INIS)

    Mashneva, N.I.

    1983-01-01

    Radiation damage to fresh water fishes at early stages of ontogenesis is revealed only during the spawn incubation in a solution with 10 -5 to 10 -3 Cu/l radioactivity and at relatively high dosages exceeding 500-1000 rad. Damaging effect of a fission product mixture of 9, 30 and 100 day age as well as of several separate radionuclides on embryogenesis of freshwater fishes depends mainly on fish species, concentration, toxicity, chemical form of radionuclides in the residence medium, on peculiarities of metabolism between the aqueous medium and an organism, stage of the embryo development by the moment of radiation effect and duration of this effect

  3. Radiological risk assessment of a radioactively contaminated site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

    A limited-scope preliminary assessment of radiological risk has been conducted at a radioactively contaminated site under current site use conditions and based on the available preliminary radiological characterization data for the site. The assessment provides useful input to the remedial action planning for the site. 8 refs., 1 fig., 2 tabs

  4. Radioactive contamination, what actions for the polluted sites

    International Nuclear Information System (INIS)

    2004-01-01

    The nuclear safety authority and the direction of prevention of pollutions and risks have organised the first edition of the national colloquium: radioactive contamination: what actions for polluted sites. Four axes can be taken to follow this colloquium: prevention, outstanding tools to evaluate risks and rehabilitation, a better responsibility of operators and memory keeping. (N.C.)

  5. Radioactive contamination from Chernobyl accident over Alexandria city

    International Nuclear Information System (INIS)

    Ammar, E.A.; El-Khatib, A.M.; Wahba, A.G.; Elraey, M.

    1987-01-01

    The concentration of radioactive contamination in air resulting from the Chernobyl accident has been followed up. A sudden and sharp increase was detected seven days after the start of the accident. This increase amounted to about 650 times the normal air-borne activity. (author)

  6. Thermoexoemission detectors for monitoring radioactive contamination of industrial waste waters

    International Nuclear Information System (INIS)

    Obukhov, V.T.; Sobolev, I.A.; Khomchik, L.M.

    1987-01-01

    Detectors on base of BeO(Na) monocrystals with thermoemission to be used for monitoring radioactive contamination of industrial waste waters are suggested. The detectors advantages are sensitivity to α and low-ehergy β radiations, high mechanical strength and wide range of measurements. The main disadvantage is the necessity of working in red light

  7. Microwave/vacuum drying treatment of radioactively contaminated animal carcasses

    International Nuclear Information System (INIS)

    Chen Zongming; Zhang Yinsheng; Teng Hongdi; Zhu Chongde; Ge Lixin; Wang Jinliang

    1994-01-01

    The paper describes a microwave/vacuum drying process for the treatment of radioactively contaminated animal carcasses. The experiment demonstrated the feasibility of the process. The treatment process could completely remove the water from carcasses and effectively extend the preservation period. No radiological impact was found on workplace and environment

  8. Protection against radioactive contamination of foods and agricultural products

    International Nuclear Information System (INIS)

    Szabo, A.; Kovacs, Z.

    1977-01-01

    Methods suitable for diminishing radioactive contamination of foods and agricultural products and reducing at the same time the irradiation hazards for the human organism are dealt with. The possibilities for the decontamination of foods vegetal and of animal origin are discussed separately. (author)

  9. Derived limits for surface contamination

    CERN Document Server

    Wrixon, A D; Linsley, G S; White, D F

    1979-01-01

    Derived limits (DLs) for surface contamination were first established for use in the nuclear energy industry where a wide variety of radionuclides is encountered. They were later used in factories, hospitals, and universities, where the radionuclides used are normally fewer in number, either known or readily identifiable, and often of low toxicity. In these situations the current limits are frequently over-restrictive. This report describes a reassessment of the values in the light of more recent information on the possible pathways of exposure and the dose equivalent limits given in ICRP Publication 26. The reassessment is prompted also by the introduction of SI units. The results of the reassessment are used to produce a classification of DLs for all radionuclides for active and inactive area surfaces and for skin.

  10. Total effective dose equivalent associated with fixed uranium surface contamination

    International Nuclear Information System (INIS)

    Bogard, J.S.; Hamm, R.N.; Ashley, J.C.; Turner, J.E.; England, C.A.; Swenson, D.E.; Brown, K.S.

    1997-04-01

    This report provides the technical basis for establishing a uranium fixed-contamination action level, a fixed uranium surface contamination level exceeding the total radioactivity values of Appendix D of Title 10, Code of Federal Regulations, part 835 (10CFR835), but below which the monitoring, posting, and control requirements for Radiological Areas are not required for the area of the contamination. An area of fixed uranium contamination between 1,000 dpm/100 cm 2 and that level corresponding to an annual total effective dose equivalent (TEDE) of 100 mrem requires only routine monitoring, posting to alert personnel of the contamination, and administrative control. The more extensive requirements for monitoring, posting, and control designated by 10CFR835 for Radiological Areas do not have to be applied for these intermediate fixed-contamination levels

  11. Radioactivity measurement of radioactive contaminated soil by using a fiber-optic radiation sensor

    Science.gov (United States)

    Joo, Hanyoung; Kim, Rinah; Moon, Joo Hyun

    2016-06-01

    A fiber-optic radiation sensor (FORS) was developed to measure the gamma radiation from radioactive contaminated soil. The FORS was fabricated using an inorganic scintillator (Lu,Y)2SiO5:Ce (LYSO:Ce), a mixture of epoxy resin and hardener, aluminum foil, and a plastic optical fiber. Before its real application, the FORS was tested to determine if it performed adequately. The test result showed that the measurements by the FORS adequately followed the theoretically estimated values. Then, the FORS was applied to measure the gamma radiation from radioactive contaminated soil. For comparison, a commercial radiation detector was also applied to measure the same soil samples. The measurement data were analyzed by using a statistical parameter, the critical level to determine if net radioactivity statistically different from background was present in the soil sample. The analysis showed that the soil sample had radioactivity distinguishable from background.

  12. Treatment of radioactive contaminated water in nuclear power plants

    International Nuclear Information System (INIS)

    1978-12-01

    This rule is to be applied to the design, construction, and operation of facilities for treatment of water contaminated with radioactive material in stationary nuclear power plants with LWRs and HTRs. According to the requirements of the rule these facilities are to be designed, constructed, and operated in such a way that a) uncontrolled discharge of water contaminated with radioactive material is avoided, b) the activity discharged with water is as low as possible, c) water contaminated with radioactive material will not reach the ground, d) the radiation exposure as a consequence of direct radiation, contamination, and inhalation of the persons occupied in the facilities is as low as possible and as a maximum corresponds to the values laid down in the radiation protection regulation or to the values of the operating license. This rule is not to be applied to facilities for coolant and storage pit clean-up as well as facilities for the treatment of concentrates produced during the contamination of the water. (orig./HP) [de

  13. Protection of environmental contamination by radioactive materials and remediation of environment

    International Nuclear Information System (INIS)

    2003-05-01

    This report consisted of the environmental contamination of radioactive and non-radioactive materials. 38 important accident examples of environmental contamination of radioactive materials in the world from 1944 to 2001 are stated. Heavily polluted areas by accidents are explained, for example, Chernobyl, atomic reactor accidents, development of nuclear weapon in USA and USSR, radioactive waste in the sea. The environmental contamination ability caused by using radioactive materials, medical use, operating reactor, disposal, transferring, crashing of airplane and artificial satellite, release are reported. It contains measurements and monitor technologies, remediation technologies of environmental contamination and separation and transmutation of radioactive materials. On the environmental contamination by non-radioactive materials, transformation of the soil contamination in Japan and its control technologies are explained. Protection and countermeasure of environmental contamination of radioactive and non-radioactive materials in Japan and the international organs are presented. There are summary and proposal in the seventh chapter. (S.Y.)

  14. Contamination and decontamination of vehicles when driven in radioactive areas

    International Nuclear Information System (INIS)

    Ulvsand, T.; Nygren, U.

    1999-10-01

    There is reason to ask whether it is beneficial to decontaminate vehicles, in view of the great effort applied. If the level of contamination is low before the decontamination process, then the cost is not motivated, even if the decontamination is shown to be effective in relative terms. The report describes two trials at the National NBC Defence School in Umeaa and one trial at the French test site in Bourges. The aim is to investigate how vehicles are contaminated and at which ground deposition levels troublesome levels of contamination will arise. In the trials, a non-radioactive agent substituting real radioactivity was used. The trials in Sweden so far have used the oversnow vehicle BV 206, during both winter and summer conditions. The vehicles were driven a specific distance along a road on which a known amount of the test substance had been dispersed. Samples were taken on pre-determined areas on one side of the vehicles to measure the amount of test substance. Later, the vehicles continued along a 'clean' road where additional samples were taken, but on the other side of the vehicles. The largest amount of test substance was collected on the tracks and on the back of the vehicle. The tracks and mud-flaps were effectively decontaminated when the vehicles were driven along a clean road, while most of the contamination remained on the backside. The purpose of the trials in France was to compare the results from our non-radioactive and their radioactive method, based on the radioactive La-140. Due to ground conditions, the level of contamination on the vehicles was much less than in the trials in Umeaa, but the effect decontamination could be measured after all

  15. Contamination and decontamination of vehicles driven in radioactive areas

    International Nuclear Information System (INIS)

    Ulvsand, T.; Nygren, U.

    1999-03-01

    There is reason to ask whether it is beneficial to decontaminate vehicles, in view of the great effort applied. If the level of contamination is low before the decontamination process, then the cost is not motivated, even if the decontamination is shown to be effective in relative terms. The report describes two trials at the National NBC Defence School in Umeaa and one trial at the French test site in Bourges. The aim is to investigate how vehicles are contaminated and at which ground deposition levels troublesome levels of contamination will arise. In the trials, a non-radioactive agent substituting real radioactivity was used. The trials in Sweden so far have used the oversnow vehicle BV 206, during both winter and summer conditions. The vehicles were driven a specific distance along a road on which a known amount of the test substance had been dispersed. Samples were taken on pre-determined areas on one side of the vehicles to measure the amount of test substance. Later, the vehicles continued along a 'clean' road where additional samples were taken, but on the other side of the vehicles. The largest amount of test substance was collected on the tracks and on the back of the vehicle. The tracks and mud-flaps were effectively decontaminated when the vehicles were driven along a clean road, while most of the contamination remained on the backside. The purpose of the trials in France was to compare the results from our non-radioactive and their radioactive method, based on the radioactive La-140. Due to ground conditions, the level of contamination on the vehicles was much less than in the trials in Umeaa, but the effect decontamination could be measured after all

  16. Radioactive contamination of oil produced from nuclear-broken shale

    International Nuclear Information System (INIS)

    Arnold, W.D.; Crouse, D.J.

    1970-01-01

    The results of small-scale exposure and retorting tests indicate that oil recovered from shale that has been broken with nuclear explosives will be contaminated with tritium. When oil shale was heated in sealed flasks with tritiated water vapor or with tritiated hydrogen, both the shale and the oil subsequently retorted from the shale contained tritium. There was much less contamination of the shale or oil, however, when the shale was exposed to tritiated methane and ethane. Contamination of shale and oil with tritium, as the result, of exposure to tritiated water, increased as the exposure temperature, exposure pressure, and the tritium concentration in the water were increased. This contamination also increased as the exposure time was increased up to 25 days, but not significantly thereafter. More than 90% of the tritium was removed from contaminated shale by treating the shale with moist air at elevated temperatures. Only small amounts of the tritium were removed from crude oil by contacting it with solid drying agents or with water. When tritium-contaminated shale oil was distilled, the tritium contents of the recovered fractions were found to be approximately equal. After being heated with a sample of underground test-shot debris, liquid shale oil became contaminated with radioactive fission products. Most of the radioactivity of the oil was due to finely dispersed solids rather than to dissolved radionuclides. Filtration of the oil removed a major fraction of the radioactive material. When the contaminated oil was distilled, more than 99% of the radionuclides remained in the pot residue. (author)

  17. Radioactive contamination of oil produced from nuclear-broken shale

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, W D; Crouse, D J

    1970-05-15

    The results of small-scale exposure and retorting tests indicate that oil recovered from shale that has been broken with nuclear explosives will be contaminated with tritium. When oil shale was heated in sealed flasks with tritiated water vapor or with tritiated hydrogen, both the shale and the oil subsequently retorted from the shale contained tritium. There was much less contamination of the shale or oil, however, when the shale was exposed to tritiated methane and ethane. Contamination of shale and oil with tritium, as the result, of exposure to tritiated water, increased as the exposure temperature, exposure pressure, and the tritium concentration in the water were increased. This contamination also increased as the exposure time was increased up to 25 days, but not significantly thereafter. More than 90% of the tritium was removed from contaminated shale by treating the shale with moist air at elevated temperatures. Only small amounts of the tritium were removed from crude oil by contacting it with solid drying agents or with water. When tritium-contaminated shale oil was distilled, the tritium contents of the recovered fractions were found to be approximately equal. After being heated with a sample of underground test-shot debris, liquid shale oil became contaminated with radioactive fission products. Most of the radioactivity of the oil was due to finely dispersed solids rather than to dissolved radionuclides. Filtration of the oil removed a major fraction of the radioactive material. When the contaminated oil was distilled, more than 99% of the radionuclides remained in the pot residue. (author)

  18. Protection against radioactive contamination of food and agricultural products

    International Nuclear Information System (INIS)

    Szabo, A.; Kovacs, Z.

    1977-01-01

    Due to contaminating effects from nuclear explosions and nuclear power plants, the systematic investigation of environmental radioactive contamination is absolutely necessary. In order to reduce the artificial radiation dose to which the human body is exposed, isotope content of foods and agricultural products should be known. The authors evaluate the decontamination possibilities of food produced from vegetable and animal products, starting from the contamination of some products. For vegetable product decontamination the use of suitable fertilizers, thorough scrubbing in excess water and, for cereals, milling is proposed. As the most effective preventive measure of radiation contamination of food products of animal origin, appropriate packing is proposed. The storage and preservation problems are emphasized for short half-life radiation contamination. (P.J.)

  19. The supposed radioactive contamination of the Puelche aquifer

    International Nuclear Information System (INIS)

    Martini, Leopoldo E.

    2005-01-01

    The paper attempts to clarify the supposed radioactive contamination of the Puelche Aquifer in the Ezeiza Atomic Center Area, Ezeiza, province of Buenos Aires (Argentina). Reports are listed that show categorically that no anthropogenic uranium contamination is present. As far as the nitrates contamination is concerned, it is not generated by the Ezeiza Atomic Center, because the Center is downward from the contaminated zone. It is possible that the contamination is produced by houses in the area without suitable sewage. In the present case the best contribution to the environmental right, besides the adaptation and the systematization of the different legal instruments, is to found the analysis of the facts on the scientific and technical knowledge. (author) [es

  20. Radioactivity contamination of the Russian Arctic Seas

    Energy Technology Data Exchange (ETDEWEB)

    Rissanen, K. [STUK Radiation and Nuclear Safety Authority, Rovaniemi (Finland); Ikaeheimonen, T.K. [STUK Radiation and Nuclear Safety Authority, Helsinki (Finland); Matishov, D.; Matishov, G.G. [Murmansk Marine Biological Inst., Murmansk (Russian Federation)

    2001-04-01

    The levels of the anthropogenic radionuclides in the Russian Arctic Seas are low compared to the potential sources of pollution and originata mainly from the global fallout, Chernobyl fallout and from the western nuclear fuel reprocessing plants. Fresh release of radioactivity was noticed in this study only in the Kola Bay and in two sampling locations in the White Sea. The increased {sup 137}Cs concentrations measured in the estuaries of River Dvina and River Yenisey are caused by the riverine transport from the large catchment area. The sediments of the Russian Arctic Seas are hard. Good and enough long cores for sedimentation rate determination were obtained only in two locations in the White Sea. All the cores from river estuaries were badly mixed. (EHS)

  1. Measurement of radioactive contamination and decontamination on wooden exteriors and garden trees in Northern Fukushima Prefecture

    International Nuclear Information System (INIS)

    Sugiura, Hiroyuki; Kawano, Keisuke; Kayama, Yukihiko

    2012-01-01

    Measurement and decontamination of surface of trees and surrounding wooden structures contaminated by radioactive substance were studied in the gardens and public parks of Northern Fukushima Prefecture which experienced radioactive contamination due to the accident at the TEPCO's Fukushima Daiichi Nuclear Power Plant. The counts per minute (CPM) above the centre surface of wooden garden tables in open air were 1.5 times higher than those of garden benches and 9 times higher than that of a garden bench in the square gazebo. Decontamination of wooden garden benches by high-pressure washing was more effective than planing. The counts per minute (CPM) above the soil around garden trees increased by 1.2 times after high-pressure washing. Radioactivity counting rate did not decrease when the leaves fallen from zelocova trees were removed; however, they decreased by about half when soil cover was installed at the base of the trees. Clearly, the upper surfaces of garden trees and wooden surrounding structures were strongly contaminated by radioactive substances, and they should be decontaminated by high-pressure washing before removing the surface soil. (author)

  2. Automatic Measurement of Low Level Contamination on Concrete Surfaces

    International Nuclear Information System (INIS)

    Tachibana, M.; Itoh, H.; Shimada, T.; Yanagihara, S.

    2002-01-01

    Automatic measurement of radioactivity is necessary for considering cost effectiveness in final radiological survey of building structures in decommissioning nuclear facilities. The RAPID (radiation measuring pilot device for surface contamination) was developed to be applied to automatic measurement of low level contamination on concrete surfaces. The RAPID has a capability to measure contamination with detection limit of 0.14 Bq/cm2 for 60Co in 30 seconds of measurement time and its efficiency is evaluated to be 5 m2/h in a normal measurement option. It was confirmed that low level contamination on concrete surfaces could be surveyed by the RAPID efficiently compared with direct measurement by workers through its actual application

  3. Environmental remediation. Strategies and techniques for cleaning radioactively contaminated sites

    International Nuclear Information System (INIS)

    Falck, W. Eberhard

    2001-01-01

    Actions for a cleaner and safety environment have risen on social and political agendas in recent years. They include efforts to remediate contaminated sites posing a radiological risk to humans and the surrounding environment. Radiological risks can result from a variety of nuclear and non-nuclear activities. They include: nuclear or radiological accidents; nuclear weapons production and testing; poor radioactive waste management and disposal practices; industrial manufacturing involving radioactive materials; conventional mining and milling of ores and other production processes, e.g. oil and gas production, resulting in enhanced concentrations of naturally occurring radioactive materials (NORMs). The IAEA has developed a comprehensive programme directed at the remediation of radioactively contaminated sites. The programme collates and distributes knowledge about contaminated sites; appropriate methods for their characterization; assessment of their potential environmental and radiological impact; and applicable methods for their clean-up, following internationally recommended safety criteria. The overall resources, and which are technologically less advanced, to focus their efforts and chose appropriate strategies for the abatement or removal of exposure to radiation. An important aspect is the intention to 'close the loop' in the nuclear fuel cycle in the interests of sustainable energy development including nuclear power

  4. Radioactive contamination in a private residence

    International Nuclear Information System (INIS)

    Marsh, W.B.E.

    1986-01-01

    A brief report is given of the contamination of a private house and garden belonging to a deceased medical physicist who had been employed by a large teaching hospital and major research organization and who had his own home laboratory. Gamma dose rates about 1.5 μSvh -1 in the laboratory, 1-2 μSvh -1 in the lounge, 0.4-0.8 μSvh -1 on items of furniture and a fireplace, 0.1 mSvh -1 in the garden shed and 0.15 to 2.0 μSvh -1 in the garden were measured. The decontamination measures performed by the NRPB to clear the area are described. (U.K.)

  5. Distinguishing method for contamination/radio-activation of radioactive wastes

    International Nuclear Information System (INIS)

    Fukazawa, Takuji; Kato, Keiichiro; Koda, Satoshi.

    1994-01-01

    The present invention concerns a method of distinguishing the contamination/radio-activation of radioactive wastes used in processing wastes generated upon dismantling of exhausted nuclear reactors. Especially, contaminated/radio-activation is distinguished for wastes having openings such as pipes and valves, by utilizing scattering of γ-rays or γ-ray to β-ray ratio. That is, ratio of scattered γ-rays and direct γ-rays or ratio of β-rays and γ-rays from radioactive wastes are measured and compared by a radiation detector, to distinguish whether the radioactive wastes contaminated materials or radio-activated materials. For example, when an object to be measured having an opening is contaminated at the inner side, the radiation detector facing to the opening mainly detects high direct γ-rays emitted from the object to be measured while a radiation detector not facing the opening mainly detects high scattered γ-rays relatively. On the other hand, when the object is a radio-activated material, any of the detectors detect scattered γ-rays, so that they can be distinguished by these ratios. (I.S.)

  6. Industrial-Scale Processes For Stabilizing Radioactively Contaminated Mercury Wastes

    International Nuclear Information System (INIS)

    Broderick, T. E.; Grondin, R.

    2003-01-01

    This paper describes two industrial-scaled processes now being used to treat two problematic mercury waste categories: elemental mercury contaminated with radionuclides and radioactive solid wastes containing greater than 260-ppm mercury. The stabilization processes were developed by ADA Technologies, Inc., an environmental control and process development company in Littleton, Colorado. Perma-Fix Environmental Services has licensed the liquid elemental mercury stabilization process to treat radioactive mercury from Los Alamos National Laboratory and other DOE sites. ADA and Perma-Fix also cooperated to apply the >260-ppm mercury treatment technology to a storm sewer sediment waste collected from the Y-12 complex in Oak Ridge, TN

  7. Radioactive contamination of honey and other bee-keeping products

    International Nuclear Information System (INIS)

    Frantsevich, L.I.; Komissar, A.D.; Levchenko, I.A.

    1990-01-01

    Great amount of dust is collected in propolis under emergency atmospheric fallouts. Specific coefficient of the product migration amounts to several m 2 per 1 kg. Propolis is a good biological indicator of radioactive fallouts. The propolis collection is inadmissible after radioactive fallouts. Cocoon residuals obtained during bees-wax separation contain many radionuclides and should be disposed in special places. Nuclides are absent in bees-wax. Nuclides accumulated absent in a bee organism migrate into honey and queen milk, the honey is contaminated mainly via biogenic path

  8. Occupational radioactive contamination of cement handlers of the civil construction

    International Nuclear Information System (INIS)

    Santos, Pedro Lopes dos; Gouvea, Rita de Cassia dos Santos; Kelecom, Alphonse; Dutra, Iedo Ramos

    1999-01-01

    Due to their occupational activities, several classes of workers are exposed to radioactive contamination by materials they handle and that contain traces of uranium and its descendants. This is the case of people that work in the civil construction and that currently handle Portland cement. Among other radioactive elements, cement contains the highly radiotoxic polonium-210 which may promote skin cancer because of its high specific activity and high LET α-particle it emits. Concentrations of polonium-210 are reported for urine, hair and skin smear of workers of the civil construction that usually handle cement. The results are compared to a control group. (author)

  9. The major regularities of the air radioactive contamination of Belarus territory after the Chernobyl accident

    International Nuclear Information System (INIS)

    Konoplya, E. F.; Mironov, V. P.; Drugachenok, M. A.; Kudryashov, V.P; Grushevich, L.E; Adamovich, A.A.

    2001-01-01

    In the first days after the Chernobyl accident the radioactivity of surface air in different regions of Belarus has increased in tens and hundred thousand time. The regular control of air radioactive contamination in the zone of alienation and nearest to it is carried out from the end 1989. The radioactive air monitoring carried out in territories with various contamination density (from 0,2 up to 9,6 MBq/m 2 on Cs-137). The measurements of the Cs-137 contents in ashes of air sampler filters were carried out by gamma - spectrometer ADCAM-300 MCA. The measurement of the Pu-240,239 and Sr-90 contents was carried out by usual radiochemical techniques. The used techniques and equipment allow to define in a sample of the minimal activity: Pu-239,240 - 0,001 Bq, Cs-137 - 0,5 Bq, Sr-90 - 0,1 Bq. The initial contamination of ground happened a near zone within approximately first 2 weeks after accident. Since the end of May, 1986 till present time the air radioactive contamination is formed under action of processes of secondary wind rise and carry of radioactive particles with contaminated territories, which depends from a number factors of both natural and anthropogenous origin. The relations of Pu-238/Pu-239 and Sr-90/Pu-239 in aerosol particles practically coincide with the same relations in fuel blown up reactor. The ratio of Cs-137/Pu-239 activities in aerosols considerably exceeds the resettlement ratio for fuel. Strontium and plutonium are in structure of fuel particles, and cesium aerosol have other origin. The analysis of changes annual radioisotopes concentration in air of towns of Belarus specifies existence of the tendency to slow decrease of contamination of atmosphere by radioisotopes of industrial origins. The basic tendency of formation of air radioactive contamination is determined by the contents of a dust at surface layer of an atmosphere and its specific activity. Annual average dust content of air in a zone resettlement was least and made about 10 mk g

  10. On-site radioactive soil contamination at the Andreeva Bay shore technical base, Northwest Russia.

    Science.gov (United States)

    Reistad, O; Dowdall, M; Selnaes, Ø G; Standring, W J F; Hustveit, S; Steenhuisen, F; Sørlie, A

    2008-07-01

    The radioactive waste (RAW) storage site at Andreeva Bay in the Russian Northwest has experienced radioactive contamination both as a result of activities carried out at the site and due to incidents that have occurred there in the past such as accidental releases of radioactive materials. The site is an interesting case study for decommissioning due to the extremely large amounts of radioactivity present at the site and the conditions under which it is stored; very little has been previously published in the scientific literature about this site. This paper complements the paper describing dose rates at Andreeva Bay which is published in this issue of Journal of Environmental Radioactivity by the same authors. This study presents new data related to the activity concentrations of (137)Cs and (90)Sr in surface soils and measurements of alpha- and beta-particle fluxes taken at different areas around the site. Limited data on 60Co is also presented. The results of the study indicate that the main areas of site contamination are associated with the former spent nuclear fuel storage facility at Building 5, due to accidental discharges which began in 1982. Substantial contamination is also observed at the solid radioactive waste storage facilities, probably due to the ingress of water into these facilities. More than 240 samples were measured: maximum contamination levels were 1 x 10(6)Bq/kg (137)Cs (mean value 4.1 x 10(5)Bq/kg) and 4 x 10(6)Bq/kg (90)Sr (mean value 1.2 x1 0(5)Bq/kg). Localised patches of alpha and beta contamination were also observed throughout the site.

  11. Analysis on the influence of forest soil characteristics on radioactive Cs infiltration and evaluation of residual radioactive Cs on surfaces.

    Science.gov (United States)

    Mori, Yoshitomo; Yoneda, Minoru; Shimada, Yoko; Fukutani, Satoshi; Ikegami, Maiko; Shimomura, Ryohei

    2018-03-29

    We investigated the depth profiles of radioactive Cs, ignition loss, and cation exchange capacity (CEC) in five types of forest soils sampled using scraper plates. We then simulated the monitored depth profiles in a compartment model, taking ignition loss as a parameter based on experimental results showing a positive correlation between ignition loss and the CEC. The calculated values were comparable with the monitored values, though some discrepancy was observed in the middle of the soil layer. Based on decontamination data on the surface dose rate and surface contamination concentration, we newly defined a surface residual index (SRI) to evaluate the residual radioactive Cs on surfaces. The SRI value tended to gradually decrease in forests and unpaved roads and was much smaller in forests and on unpaved roads than on paved roads. The radioactive Cs was assumed to have already infiltrated underground 18 months after the nuclear power plant accident, and the sinking was assumed to be ongoing. The SRI values measured on paved roads suggested that radioactive Cs remained on the surfaces, though a gradual infiltration was observed towards the end of the monitoring term. The SRI value is thought to be effective in grasping the rough condition of residual radioactive Cs quickly at sites of decontamination activity in the field. The SRI value may be serviceable for actual contamination works after further research is done to elucidate points such as the relation between the SRI and the infiltration of radioactive Cs in various types of objects.

  12. A model for evaluating the radioactive contamination in the urban environment

    International Nuclear Information System (INIS)

    Hwang, Won Tae; Kim, Eun Han; Jeong, Hyo Joon; Suh, Kyung Suk; Han, Moon Hee

    2005-01-01

    A model for evaluating radioactive contamination in the urban environment, named METRO-K, was developed as a basic step for accident consequence analysis in case of an accidental release. The three kind of radionuclides ( 137 Cs, 106 Ru, 131 I) and the different chemical forms of iodine (particulate, organic and elemental forms) are considered in the model. The radioactive concentrations are evaluated for the five types of surface (roof, paved road, wall, lawn/soil, tree) as a function of time. Using the model, the contaminative impacts of the surfaces were intensively investigated with respect to with and without precipitation during the measurement periods of radionuclides in air. In addition, a practical application study was conducted using 137 Cs concentration in air and precipitation measured in an European country at the Chernobyl accident. As a result, precipitation was an influential factor in surface contamination. The degree of contamination was strongly dependent on the types of radionuclide and surface. Precipitation was more influential in contamination of 137 Cs than that of 131 I (elemental form)

  13. Treatment of Gravel Contaminated with Naturally Occurring Radioactive Element

    International Nuclear Information System (INIS)

    Sohsah, M. A.; Kamal, S. M.; Mamoon, A.

    2004-01-01

    Environmental protection primarily means controlling the releases of radioactive and non-radioactive wastes to the environment and involves treatment, storage, cleanup and disposal of these wastes. The present study concerns the cleanup of gravel that has been contaminated with 2 26 R a. Aqueous solutions of different compositions including water and various concentrations of calcium chloride and barium chloride were used to leach the contaminated gravel. The leaching experiments were carried out in glass column. In some leaching experiments, samples of sandy soil were placed below the gravel to test the sorption of the leached 2 26 R a by the soil. The relative efficiencies of the leachant and the extent of sorption of the leached radionuclide were determined both by the liquid scintillation counting and by the thermoluminescent chips. The TLD chips record the dose before and after decontamination of the gravel and before and after contamination of the soil samples when used. The results obtained indicated that acidified barium chloride was relatively the most effective leachant of 2 26 R a contamination. It reduced the dose from the contaminated gravel to almost half. The soil sample used adsorbs the leached radionuclides efficiently, increasing the soil naturally low dose to about six folds

  14. Dosskin code for radiological evaluation of skin radioactive contaminations

    International Nuclear Information System (INIS)

    Cornejo D, N.

    1996-01-01

    The conceptual procedure and computational features of the DOSSKIN code are shown. This code calculates, in a very interactive way, skin equivalent doses and radiological risk related to skin radioactive contaminations. The evaluation takes into account the contributions of contaminant daughter nuclides and backscattering of beta particles in any skin cover. DOSSKIN also allows to estimate the maximum time needed to decontaminate the affected zone, using, as input quantity, the limit value of skin equivalent dose considered by users. The comparison of the results obtained by the DOSSKIN code with those reported by different authors are showed. The differences of results are less than 30%. (authors). 4 refs., 3 fig., 1 tab

  15. Protection of atmospheric air against radioactive gas and aerosol contaminants

    International Nuclear Information System (INIS)

    Zykova, A.S.

    1984-01-01

    Measures for contamination protection of atmospheric air subdivided into active and passive ones, are considered. The active measures envisage: development and application of waste-free flowsheets, use of flowsheets which restrict formation of gaseous-aerosol discharges; application of highly efficient treatment facilities torage. Dispersion of radioactive substances, released with discharges to the atmosphere, using high stacks; development of the corresponding site-selection solutions and arrangement of sanitary protective zones belong to passive measures. Measures for protection of atmospheric air also include waste and air contamination monitoring. The measures described are considered as applied to NPPs

  16. Internal radioactive contamination in selected groups of CRNL employees

    International Nuclear Information System (INIS)

    Evans, D.W.S.

    1975-10-01

    This report details the development and execution of a 30 month program designed to characterize the magnitude and distribution of internal radioactive contaminaton amongst selected groups of employees at Chalk River Nuclear Laboratories, using a shadow shield whole-body counter. The results show that the levels of contamination in these employees are very low, and no contaminant was present in amounts exceeding 10% of the maximum permissible body burden, with the exception of a medically administered radionuclide (selenium-75). Details of the time course of some of the body burdens are also furnished. (author)

  17. Decontamination and radioactivity measurement on building surfaces related to dismantling of Japan power demonstration reactor (JPDR)

    International Nuclear Information System (INIS)

    Hatakeyama, Mutsuo; Tachibana, Mitsuo; Yanagihara, Satoshi

    1997-12-01

    In the final stage of dismantling activities for decommissioning a nuclear power plant, building structures have to be demolished to release the site for unrestricted use. Since building structures are generally made from massive reinforced concrete materials, it is not a rational way to treat all concrete materials arising from its demolition as radioactive waste. Segregation of radioactive parts from building structures is therefore indispensable. The rational procedures were studied for demolition of building structures by treating arising waste as non-radioactive materials, based on the concept established by Nuclear Safety Commission, then these were implemented in the following way by the JPDR dismantling demonstration project. Areas of the JPDR facilities are categorized into two groups : possibly contaminated areas, and possibly non-contaminated areas, based on the document of the reactor operation. Radioactivity on the building surfaces was then measured to confirm that the qualitative categorization is reasonable. After that, building surfaces were decontaminated in such a way that the contaminated layers were removed with enough margin to separate radioactive parts from non-radioactive building structures. Thought it might be possible to demolish the building structures by treating arising waste as non-radioactive materials, confirmation survey for radioactivity was conducted to show that there is no artificial radioactive nuclides produced by operation in the facility. This report describes the procedures studied on measurement of radioactivity and decontamination, and the results of its implementation in the JPDR dismantling demonstration project. (author)

  18. Vitrification of radioactive contaminated soil by means of microwave energy

    Science.gov (United States)

    Yuan, Xun; Qing, Qi; Zhang, Shuai; Lu, Xirui

    2017-03-01

    Simulated radioactive contaminated soil was successfully vitrified by microwave sintering technology and the solidified body were systematically studied by Raman, XRD and SEM-EDX. The Raman results show that the solidified body transformed to amorphous structure better at higher temperature (1200 °C). The XRD results show that the metamictization has been significantly enhanced by the prolonged holding time at 1200 °C by microwave sintering, while by conventional sintering technology other crystal diffraction peaks, besides of silica at 2θ = 27.830°, still exist after being treated at 1200 °C for much longer time. The SEM-EDX discloses the micro-morphology of the sample and the uniform distribution of Nd element. All the results show that microwave technology performs vitrification better than the conventional sintering method in solidifying radioactive contaminated soil.

  19. Sites in the United States contaminated with radioactivity

    International Nuclear Information System (INIS)

    Wolbarst, A.B.; Blom, P.F.; Chan, D.

    1999-01-01

    Over the century that radioactive materials have been mined, processed, produced, and utilized, many sites across the US have become contaminated. Such sites include bases and installations of the Department of Defense, weapons production and research facilities of the Department of Energy, properties under the authority of other Federal agencies, privately-owned and governmental facilities that are licensed by the Nuclear Regulatory Commission and its Agreement States, and sites licensed by or the responsibility of states. This review reports on aspects of work by the Environmental Protection Agency, the Department of Defense, the Department of Energy, the Nuclear Regulatory Commission, and others to identify sites contaminated with radioactive materials. It also describes the principal programs that have been instituted to deal with them

  20. Disposal sheet for preventing scattering of radioactive contaminated material

    International Nuclear Information System (INIS)

    Miyasaka, Shun-ichi; Kurioka, Hitoshi; Nakamura, Kenjiro.

    1990-01-01

    Upon disposal of vinyl sheets at the final stage of dismantling operation for nuclear buildings, etc., radioactive contaminated materials caused by cutting concretes, etc. remain on the sheets. In view of the above, members capable of restoring original shape due to the temperature difference are attached to the sheet main body so that the sheet main body may be folded into a bag-like shape. Since the members as described above are bent upon temperature elevation in the sheets, the sheet main body is pulled by the members and then spontaneously folded into a bag-like shape. As a result, the radioactive contaminated materials remaining on the sheets are wrapped into the sheet main body free from touch to operator's hands or without scattering to the surrounding. This can prevent operator's external and internal exposure. (T.M.)

  1. REAL-TIME IDENTIFICATION AND CHARACTERIZATION OF ASBESTOS AND CONCRETE MATERIALS WITH RADIOACTIVE CONTAMINATION

    International Nuclear Information System (INIS)

    XU, X. George; Zhang, X.C.

    2002-01-01

    Concrete and asbestos-containing materials were widely used in DOE building construction in the 1940s and 1950s. Over the years, many of these porous materials have been contaminated with radioactive sources, on and below the surface. To improve current practice in identifying hazardous materials and in characterizing radioactive contamination, an interdisciplinary team from Rensselaer has conducted research in two aspects: (1) to develop terahertz time-domain spectroscopy and imaging system that can be used to analyze environmental samples such as asbestos in the field, and (2) to develop algorithms for characterizing the radioactive contamination depth profiles in real-time in the field using gamma spectroscopy. The basic research focused on the following: (1) mechanism of generating of broadband pulsed radiation in terahertz region, (2) optimal free-space electro-optic sampling for asbestos, (3) absorption and transmission mechanisms of asbestos in THz region, (4) the role of asbestos sample conditions on the temporal and spectral distributions, (5) real-time identification and mapping of asbestos using THz imaging, (7) Monte Carlo modeling of distributed contamination from diffusion of radioactive materials into porous concrete and asbestos materials, (8) development of unfolding algorithms for gamma spectroscopy, and (9) portable and integrated spectroscopy systems for field testing in DOE. Final results of the project show that the combination of these innovative approaches has the potential to bring significant improvement in future risk reduction and cost/time saving in DOE's D and D activities

  2. Radioactive waste and contamination in the former Soviet Union

    International Nuclear Information System (INIS)

    Suokko, K.; Reicher, D.

    1993-01-01

    Decades of disregard for the hazards of radioactive waste have created contamination problems throughout the former Soviet Union rivaled only by the Chernobyl disaster. Although many civilian activities have contributed to radioactive waste problems, the nuclear weapons program has been by far the greatest culprit. For decades, three major weapons production facilities located east of the Ural Mountains operated in complete secrecy and outside of environmental controls. Referred to until recently only by their postal abbreviations, the cities of Chelyabinsk-65, Tomsk-7, and Krasnoyarsk-26 were open only to people who worked in them. The mismanagement of waste at these sites has led to catastrophic accidents and serious releases of radioactive materials. Lack of public disclosure, meanwhile, has often prevented proper medical treatment and caused delays in cleanup and containment. 5 refs

  3. Radioactive contamination: atlas France and Europe. French soils contamination by Chernobyl accident fallouts - The lie evidences

    International Nuclear Information System (INIS)

    Paris, Andre; Castanier, Corinne

    2002-01-01

    This document deals with the Chernobyl nuclear accident impacts and the authorities transparency. The first part is a reference document constituted by the CRIIRAD and showing how the authorities strove for minimizing the real contamination of French soils by the Chernobyl fallouts. In the second part, an atlas provides the detailed maps of the radioactive contamination of soils based on more than 3000 measurements carried out by a geologist, Andre Paris, assisted by the CRIIRAD laboratory

  4. Radioactive contamination of protective clothes made of textile and their decontamination in aqueous solutions

    International Nuclear Information System (INIS)

    Fukumori, D.T.

    1989-01-01

    This dissertation deals with the radioactive contamination, its prevention, control and decontamination, related to protective clothing made of textile and usually weared in normal working conditions, within the installations where radioactive materials are handled or processed, especially as unsealed sources. The features of textile materials and contaminants, contamination mechanisms, risks related to contaminated clothes, planning of working areas, monitoring and surface contamination limits are described. Concerning to decontamination, the reagents, their action mechanisms and methods of efficiency evaluation are emphasized. The selected reagents were experimentally tested and their efficiencies in decontaminating cotton cloth samples, contaminated with uranyl nitrate solution, were evaluated by means of counting rate determined with a Geiger-Muller provided counting system. In this way, complexing agents, surfactants and commercial cleanning products were tested. The results were analysed and interpreted considering statistical, radiochemical and Radiation Protection aspects. Both, the radiactive contamination and decontamination of protective clothes are extensive matters and they still could be developed and improved; thus, many suggestions were presented as further studies. (author) [pt

  5. Applicability of monitored natural attenuation at radioactively contaminated sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

    The IAEA attaches great importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support a sustainable nuclear fuel cycle and nuclear applications, including managing the legacy of past practices and accidents. Hence, the IAEA has initiated a comprehensive programme of work covering all aspects of environmental remediation including: - Technical and non-technical factors influencing decision making in environmental remediation; - Site characterization techniques and strategies; - Assessment of remediation technologies; - Assessment of technical options for cleanup of contaminated media; - Post-restoration compliance monitoring; - Assessment of the costs of remediation measures. It has been observed that many measures to remove or contain contamination are inefficient below certain concentrations, in general costly, and of a limited lifetime compared with the half-lives of the radionuclides concerned. Dispersed low level contamination poses a particular challenge to those charged with its remediation. Economic considerations in many Member States also result in constraints being placed on resources available to deal with such contamination. Experience has also shown that many techniques are not efficient below certain concentration thresholds or may entail impacts on certain environmental compartments in addition to those due to the contamination itself. This includes doses received by workers on the remediation project. As a result, the concept of relying on geological media to retain contaminants and/or to 'flatten out' concentration/dose peaks is increasingly being discussed in a remediation context. Technical Reports Series No. 424 (Remediation of Sites with Dispersed Radioactive Contamination) examined a variety of technological options for remediating dispersed contamination and concluded that the approaches can be broadly

  6. Applicability of monitored natural attenuation at radioactively contaminated sites

    International Nuclear Information System (INIS)

    2006-01-01

    The IAEA attaches great importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support a sustainable nuclear fuel cycle and nuclear applications, including managing the legacy of past practices and accidents. Hence, the IAEA has initiated a comprehensive programme of work covering all aspects of environmental remediation including: - Technical and non-technical factors influencing decision making in environmental remediation; - Site characterization techniques and strategies; - Assessment of remediation technologies; - Assessment of technical options for cleanup of contaminated media; - Post-restoration compliance monitoring; - Assessment of the costs of remediation measures. It has been observed that many measures to remove or contain contamination are inefficient below certain concentrations, in general costly, and of a limited lifetime compared with the half-lives of the radionuclides concerned. Dispersed low level contamination poses a particular challenge to those charged with its remediation. Economic considerations in many Member States also result in constraints being placed on resources available to deal with such contamination. Experience has also shown that many techniques are not efficient below certain concentration thresholds or may entail impacts on certain environmental compartments in addition to those due to the contamination itself. This includes doses received by workers on the remediation project. As a result, the concept of relying on geological media to retain contaminants and/or to 'flatten out' concentration/dose peaks is increasingly being discussed in a remediation context. Technical Reports Series No. 424 (Remediation of Sites with Dispersed Radioactive Contamination) examined a variety of technological options for remediating dispersed contamination and concluded that the approaches can be broadly

  7. Responses of the soil decomposer community to the radioactive contamination

    International Nuclear Information System (INIS)

    Svetlana, Maksimova

    2004-01-01

    The knowledge about biodiversity and about reasons and laws of dynamics of decomposer invertebrates has exclusively important (rather applied, or theoretical) significance for soil science. Earthworms and millipedes are probably the most important members of the soil biota and major contributors to total zoo-mass. Their activities are such that they are extremely important in maintaining soil fertility in a variety of ways. They play an important part in the redistribution of radionuclides accumulated in the natural biogeocenoses and accumulation of radionuclides in their bodies depends on their concentration in the habitat. Since radionuclides can limit biological activity, studies to estimate the tolerance of decomposer community to potentially toxic radiators are needed. The effect of radioactive contamination on the soil invertebrates and decomposition processes in the different biogeocenoses we intensively studied during 17 years after Chernobyl accident. The soil invertebrates were collected according to generally accepted method by M. Ghilyarov. Soil samples were 0,25 m 2 and animals were extracted from samples by hand sorting. Usually decomposition was affected by the presence of decomposer fauna. Considerable differences were found in the species number. The species composition of sites differed clearly. The study showed that the fauna was poorer under increasing levels of radioactive contamination. The higher radionuclide content was found to result in suppression of decomposer community. The results showed a vertical migration of earthworms to deeper soil layers with increasing of radioactive contamination. With the absence of decomposer fauna due to migration to the deeper layer and mortality, the layer of litter increased. The results show that the earthworms were of small size. Cocoon production decreased. Radioactive contamination altered the process of reproduction and age structure of decomposer fauna. The invertebrates collected from the

  8. Responses of the soil decomposer community to the radioactive contamination

    Energy Technology Data Exchange (ETDEWEB)

    Svetlana, Maksimova [Institute of Zoology of National Academy of Sciences of Belarus, Minsk (Belarus)

    2004-07-01

    The knowledge about biodiversity and about reasons and laws of dynamics of decomposer invertebrates has exclusively important (rather applied, or theoretical) significance for soil science. Earthworms and millipedes are probably the most important members of the soil biota and major contributors to total zoo-mass. Their activities are such that they are extremely important in maintaining soil fertility in a variety of ways. They play an important part in the redistribution of radionuclides accumulated in the natural biogeocenoses and accumulation of radionuclides in their bodies depends on their concentration in the habitat. Since radionuclides can limit biological activity, studies to estimate the tolerance of decomposer community to potentially toxic radiators are needed. The effect of radioactive contamination on the soil invertebrates and decomposition processes in the different biogeocenoses we intensively studied during 17 years after Chernobyl accident. The soil invertebrates were collected according to generally accepted method by M. Ghilyarov. Soil samples were 0,25 m{sup 2} and animals were extracted from samples by hand sorting. Usually decomposition was affected by the presence of decomposer fauna. Considerable differences were found in the species number. The species composition of sites differed clearly. The study showed that the fauna was poorer under increasing levels of radioactive contamination. The higher radionuclide content was found to result in suppression of decomposer community. The results showed a vertical migration of earthworms to deeper soil layers with increasing of radioactive contamination. With the absence of decomposer fauna due to migration to the deeper layer and mortality, the layer of litter increased. The results show that the earthworms were of small size. Cocoon production decreased. Radioactive contamination altered the process of reproduction and age structure of decomposer fauna. The invertebrates collected from the

  9. Residual radioactive contamination at Maralinga and Emu, 1985

    International Nuclear Information System (INIS)

    Lokan, K.H.

    1985-04-01

    An account is provided of residual contamination at Maralinga and Emu, in South Australia, where the United Kingdom Atomic Weapons Research Establishment conducted nuclear weapons development trials between 1953 and 1963. Detailed information is presented about contamination levels at sites on the range where radioactive materials were dispersed. Some of these were associated with trials involving natural uranium or short-lived isotopes which are no longer present. There are four sites where plutonium-239 was dispersed in substantial quantities from minor trials and information is presented about its distribution. Much of this material has been diluted by mixing with local soil, but there is a significant quantity of material present in the form of contaminated fragments, particularly at Taranaki. A considerable quantity of uranium-235 is also present at Taranaki. An assessment is made of the radiological significance of the dispersed plutonium and it is concluded that the material represents a potential long term hazard while it remains in its present form. Residual radioactivity associated with all but one of the seven major trial sites involving nuclear explosions continues to decay in a predictable way and will in the worst case, fall below levels considered safe for continuous occupancy within about fifty years. One site, Tadje, contains significant concentrations of plutonium over a small area and onsidered to be an additional plutonium-contaminated locality. Measurements of beryllium concentrations in soil are presented

  10. Waste processing system for product contaminated with radioactivity

    International Nuclear Information System (INIS)

    Sotoyama, Koichi; Takaya, Jun-ichi; Takahashi, Suehiro.

    1987-01-01

    Purpose: To enable to processing contaminated products while separating them into metals at high contamination level and non-metals at low contamination level. Constitution: Pulverized radioactive wastes conveyed on a conveyor belt are uniformly irradiated by a ring-illumination device and then they are picked-up by a television camera or the like. The picked-up signals are sent to an image processing device, applied with appropriate binarization and metal objects are separated by utilizing the light absorbing property of non-metal and light reflection property of metals. The graviational center for the metal object is calculated from the binarized image, the positional information is provided to a robot controller and the metal object is transferred to another position by a robot. Since only the metal object at high radioactive contamination level can be taken out separately, it is no more necessary to process the entire wastes as the high level decontamination products, to thereby provide an economical advantage. (Sekiya, K.)

  11. The accumulation of radioactive contaminants in drinking water distribution systems.

    Science.gov (United States)

    Lytle, Darren A; Sorg, Thomas; Wang, Lili; Chen, Abe

    2014-03-01

    The accumulation of trace contaminants in drinking water distribution system sediment and scales has been documented, raising concerns that the subsequent release of the contaminants back to the water is a potential human exposure pathway. Radioactive contaminants are of concern because of their known health effects and because of their persistence within associated distribution system materials. The objective of this work was to measure the amount of a number of radioactive contaminants (radium, thorium, and uranium isotopes, and gross alpha and beta activity) in distribution solids collected from water systems in four states (Wisconsin, Illinois, Minnesota, and Texas). The water utilities chosen had measurable levels of radium in their source waters. In addition, 19 other elements in the solids were quantified. Water systems provided solids primarily collected during routine fire hydrant flushing. Iron was the dominant element in nearly all of the solids and was followed by calcium, phosphorus, magnesium, manganese, silicon, aluminum and barium in descending order. Gross alpha and beta radiation averaged 255 and 181 pCi/g, and were as high as 1602 and 1169 pCi/g, respectively. Total radium, thorium and uranium averaged 143, 40 and 6.4 pCi/g, respectively. Radium-226 and -228 averaged 74 and 69 pCi/g, and were as high as 250 and 351 pCi/g, respectively. Published by Elsevier Ltd.

  12. General radioactive contamination of the biosphere measurements in the Netherlands 1974. Annual report Coordination Commission radioactivity measurements and Coordination Commission for the measurements of radioactivity and xenobiotic materials

    Energy Technology Data Exchange (ETDEWEB)

    1975-07-01

    For several years, measurements have been performed in the Netherlands to determine radioactive contamination of the biosphere. These measurements are carried out by various institutes responsible to three ministries: the Ministery of 'Health and Environmental Protection', of 'Agriculture and Fisheries' and of 'Transport and Water', (Dutch: 'Verkeer en Waterstaat', under the supervision of the Coordination Commission Radioactive Measurements (CCRA)). Besides radionuclides, many other elements and compounds are considered harmful for man, animal and the environment. A systematic control of the extent of the contamination of the biosphere, in the same way as is in operation for radionuclides, has been proposed for a number of the most harmful contaminants of the biosphere. The measurements are divided into measurements for the National Measuring Programme and additional Measurements. The former include the analyses essential for an efficacious control of the radioactivity of the biosphere. Measurements are performed in air, soil, surface water, milk and in deposition on the surface of the earth. Besides the determination of the usual radionuclides, as performed up to 1970, deposited radioactivity and surface water are also tested for some other specific radionuclides which may be set free at nuclear installations. Finally, samples of milk and grass from the surroundings of nuclear reactors and water from drinking-waterreservoirs have been analysed. Results are given of determination of tritium in drinking water of four big cities, and of radionuclides in some fishery products from the Dutch coastal waters in view of the potential of some marine organisms to concentrate fission products and especially activated corrosion products from nuclear installations. Adiitionally are given the results of measurements by the licensees of the Dutch nuclear installations of samples from the surroundings of their plants.

  13. Assessment and prediction of the scales of radioactive contamination of the environment by emissions from a nuclear power plant

    International Nuclear Information System (INIS)

    Elokhin, A.P.; Solovei, A.F.

    1995-01-01

    The assessment of radioactive contamination of the air basin and underlying surface in the direction of emission reduces to determining the volume activity of the radioactive impurity in air, the surface activity on the underlying surface of the radioactive impurity is known at least approximately (for example, it can be set on the basis of the technological regulations at the nuclear power plant or according to the criterion of levels during an accident), by using exposure-dose-rate sensors in a network of posts of the automatic system for monitoring the radiation environment (ASMRE), which are placed on the industrial area of the nuclear power plant, in the shielded zone and in the observation zone, it is possible to determine more accurately the magnitude of the emission and, therefore, to estimate the scale of the radioactive contamination of the medium

  14. Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

    International Nuclear Information System (INIS)

    Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K.

    2001-04-01

    The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology

  15. Latest movements associated with radioactive contamination and disaster waste management

    International Nuclear Information System (INIS)

    Omura, Tomomi

    2012-01-01

    As for the radioactive contamination countermeasures taken for the accident of the Fukushima Daiichi Nuclear Station of Tokyo Electric Power Company, this paper introduces in the digest version the following movements from early March to early April 2012. (1) Organizational structure. Inauguration of Nuclear Regulatory Agency, and the organizational structure of Fukushima Environment Regeneration Office of the Ministry of the Environment. (2) The Act on Special Measures concerning the Handling of Radioactive Pollution. Publication by the Ministry of the Environment on decontamination plan for three municipalities belonging to Special Decontamination Area, decontamination plan for Intensive Contamination Survey Area, new construction of disposal sites for designated waste with the level exceeding 8,000 Bq / kg, and disaster waste direct treatment project and substitute treatment project in Fukushima Prefecture. (3) Radiation exposure countermeasures. Lawmaker-initiated registration plan by Democratic Party, Liberal Democratic Party, and New Komeito. (4) Technological evaluation. Publication of the results of Decontamination Technology Demonstration Test Projects by the Cabinet Office, the Ministry of the Environment, and Fukushima Prefecture. (5) Monitoring. Full-scale implementation of radioactivity monitoring plan in Tokyo Bay in Fiscal 2012. (6) Disaster waste countermeasures. Request of the government to the local governments on the wide-area treatment of wreckage, active request to the Cement Association in cooperation with the treatment of wreckage, and positive replies from of 22 prefectures / cities regarding the acceptance of wide-area wreckage treatment. (O.A.)

  16. Development of portable and automatic smear sampler for measuring surface contamination

    International Nuclear Information System (INIS)

    Lee, Bong Jae; Chang, S. Y.; Kim, B. H.; Kim, J. S.; Lee, H. S.; Kim, C. K.; Swol, C. W.

    2000-12-01

    In measuring radioactive contamination in radiation controlled area of nuclear facility, the technical criteria to evaluate surface contamination level and to sample by indirect method was established in this paper. Radioactive materials always present on surface within operating nuclear facilities. Because of the presence of interfering radiation field, health physicists take smear samples to monitoring surface contamination according to routine monitoring program. But there are some problems like great errors and difference of personnel. Then, to solve them, The portable and automatic smear sampling apparatus was designed and fabricated

  17. Development of portable and automatic smear sampler for measuring surface contamination

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Bong Jae; Chang, S. Y.; Kim, B. H.; Kim, J. S.; Lee, H. S.; Kim, C. K.; Swol, C. W

    2000-12-01

    In measuring radioactive contamination in radiation controlled area of nuclear facility, the technical criteria to evaluate surface contamination level and to sample by indirect method was established in this paper. Radioactive materials always present on surface within operating nuclear facilities. Because of the presence of interfering radiation field, health physicists take smear samples to monitoring surface contamination according to routine monitoring program. But there are some problems like great errors and difference of personnel. Then, to solve them, The portable and automatic smear sampling apparatus was designed and fabricated.

  18. Health assessment for Monticello Radioactive Contaminated Properties, Monticello, Utah, Region 8. CERCLIS No. UTD980667208. Preliminary report

    International Nuclear Information System (INIS)

    1989-01-01

    The Monticello Mill Site (MMS) is on the National Priorities List. The site is located in Monticello (San Juan County), Utah. MMS includes properties contaminated with radioactive ore wastes from a former uranium mill located near the town. The mill was formerly operated by the Atomic Energy Commission and is now the responsibility of the Department of Energy. Radioactive contaminants (uranium, radium, thorium, and radon) are present in mine tailings, soil, ground water, and surface water on-site and also in ground water, surface water, and soil off-site. Based on available information, the site is considered to be of public health concern because of the risk to human health caused by the likelihood of human exposure to hazardous substances. The possibility exists that human exposure could occur from domestic use of contaminated ground water, consumption of commercial crops, garden vegetables grown in contaminated soil, and consumption of commercial livestock that graze on contaminated soil, grasses, and feed

  19. A Novel Method for Remote Depth Estimation of Buried Radioactive Contamination.

    Science.gov (United States)

    Ukaegbu, Ikechukwu Kevin; Gamage, Kelum A A

    2018-02-08

    Existing remote radioactive contamination depth estimation methods for buried radioactive wastes are either limited to less than 2 cm or are based on empirical models that require foreknowledge of the maximum penetrable depth of the contamination. These severely limits their usefulness in some real life subsurface contamination scenarios. Therefore, this work presents a novel remote depth estimation method that is based on an approximate three-dimensional linear attenuation model that exploits the benefits of using multiple measurements obtained from the surface of the material in which the contamination is buried using a radiation detector. Simulation results showed that the proposed method is able to detect the depth of caesium-137 and cobalt-60 contamination buried up to 40 cm in both sand and concrete. Furthermore, results from experiments show that the method is able to detect the depth of caesium-137 contamination buried up to 12 cm in sand. The lower maximum depth recorded in the experiment is due to limitations in the detector and the low activity of the caesium-137 source used. Nevertheless, both results demonstrate the superior capability of the proposed method compared to existing methods.

  20. Issues facing the management of radioactively contaminated lead within the DOE system

    International Nuclear Information System (INIS)

    Gilmore, M.C.; Kent, S.H.

    1993-01-01

    The purpose of this paper is to discuss and evaluate the issues that managing and operating contractors in the US DOE system should consider that are associated with management of radioactively contaminated elemental lead. There are many instances where DOE contaminated lead fall within Resource Conservation and Recovery Act (RCRA) regulation. In light of the Federal Facilities Compliance Act (FFCA), it is becoming increasingly important for additional regulatory options to be explored in order to facilitate proper treatment, storage and disposal of RCRA regulated lead. Various DOE facilities have initiated processes to reuse or recycle contaminated lead. Technologies such as melt-refining, surface blasting, and electromigration are being explored. One or more of these technologies may be the key to reducing contaminated lead inventories in the DOE system. Many DOE facilities are finding that these efforts need to have stringent regulatory evaluation since some alternatives have proven to be environmentally desirable but not economically feasible

  1. Radioactive contamination of the Dutch soil in consequence of the nuclear reactor accident at Chernobyl

    International Nuclear Information System (INIS)

    Koester, H.W.; Mattern, F.C.M.; Pennders, R.M.J.

    1987-01-01

    As a consequence of the reactor accident in Chernobyl air, contaminated with radioactive materials, spread over the Netherlands. From 2nd May to 6th May, with dry and to a greater extent with wet deposits, important quantities of radionuclides came upon the earth surface. In this period the weather circumstances within the Netherlands differed strongly resulting in distinct variations in deposit. In this document a preliminary picture is given of the contamination of the Dutch bottom on the basis of soil samplings made in the first few months after the accident. No attention is paid to geographic differences in bottom contamination. The contamination of the bottom is expressed in Bq/kg dry soil as well as in Bq/m 2 soil. 5 refs.; 6 tabs. (H.W.)

  2. Characterization of radioactively contaminated sites for remediation purposes

    International Nuclear Information System (INIS)

    1998-05-01

    Characterization of the contaminated site is essential before embarking on a programme for its remediation and ultimate restoration. Reliable and suitable data must be obtained regarding the distribution and physical, chemical and nuclear properties of all radioactive contaminants. Characterization data is necessary for assessing the associated radiation risks and is used in support of the required engineering design and project planning for the environmental restoration. In addition, continuing characterization can provide information regarding efficiency of the cleanup methods and influence possible redirection of work efforts. Similarly, at the end of the remediation phase, characterization and ongoing monitoring can be used to demonstrate completion and success of the cleanup process. The suggested methodology represents a contribution attempting to solve the issue of preremediation characterization in a general manner. However, a number of difficulties might make this methodology unsuitable for general application across the diverse social, environmental and political systems in the IAEA Member States. This TECDOC covers the methodologies used to characterize radioactively contaminated sites for the purpose of remediating the potential sources of radiation exposure and assessing the hazards to human health and the environment

  3. Techniques for removing contaminated concrete surfaces

    International Nuclear Information System (INIS)

    Halter, J.M.; Sullivan, R.G.

    1981-01-01

    This discussion compares various techniques that have been used to clean concrete surfaces by removing the surface. Three techniques which have been investigated by the Pacific Northwest Laboratory for removing surfaces are also described: the water cannon, the concrete spaller, and high-pressure water jet. The equipment was developed with the assumption that removal of the top 1/8 to 1/4 in. of surface would remove most of the contamination. If the contamination has gone into cracks or deep voids in the surface, the removal processes can be repeated until the surface is acceptable

  4. Environmental review of options for managing radioactively contaminated carbon steel

    International Nuclear Information System (INIS)

    1996-10-01

    The U.S. Department of Energy (DOE) is proposing to develop a strategy for the management of radioactively contaminated carbon steel (RCCS). Currently, most of this material either is placed in special containers and disposed of by shallow land burial in facilities designed for low-level radioactive waste (LLW) or is stored indefinitely pending sufficient funding to support alternative disposition. The growing amount of RCCS with which DOE will have to deal in the foreseeable future, coupled with the continued need to protect the human and natural environment, has led the Department to evaluate other approaches for managing this material. This environmental review (ER) describes the options that could be used for RCCS management and examines the potential environmental consequences of implementing each. Because much of the analysis underlying this document is available from previous studies, wherever possible the ER relies on incorporating the conclusions of those studies as summaries or by reference

  5. Prevention and mitigation of groundwater contamination from radioactive releases

    International Nuclear Information System (INIS)

    1988-10-01

    This document gives basic information on potential pathways and mechanisms, by which radioactive materials from releases can reach man, and on modelling considerations to predict the behaviour of radioactive materials in the ground. The main objective is to present an overview of existing techniques for preventing the offsite releases of contaminants into the groundwater systems and techniques for mitigation of effects of such releases should they occur. The recommended techniques are fully applicable to any hazardous materials, such as organic liquids, and toxic materials or otherwise dangerous materials, the presence of which in the accessible biosphere can represent health risks as well as economic losses to the general public. 11 refs, 2 figs, 8 tabs

  6. Sources to radioactive contamination in Murmansk and Arkhangelsk counties

    International Nuclear Information System (INIS)

    Nilsen, T.; Boehmer, N.

    1994-02-01

    The report gives a general view of information gathered by the Bellona Foundation on the use of nuclear energy, as well as storage and processing of radioactive waste in the region. Information has been collected since 1989 through extensive field work in the Russian Federation. During the gathering of source material for the report, crucial importance has been attached to Russian sources encountered during the field work. The report intends to present a survey of the various sources of possible radioactive pollution, and the historical background for placing the sources in the region. As it appears from the report, the most significant contamination source is the military activity. The Bellona Foundation has made a point of describing the sources only on a technical base, and no attempts have been made to evaluate risks and consequences of conceivable accidents. 78 refs

  7. Health effects associated with exposure to radioactively contaminated gold rings

    International Nuclear Information System (INIS)

    Baptiste, M.S.; Rothenberg, R.; Nasca, P.C.; Janerich, D.T.; Stutzman, C.D.; Rimawi, K.; O'Brien, W.; Matuszek, J.

    1984-01-01

    This study was designed to assess the health risks associated with exposure to radioactively contaminated gold rings. A group of 135 exposed individuals, who were identified through a statewide jewelry screening program, were studied to determine the frequency of carcinoma and other skin problems on the ring finger. Severity of skin problems increased with increasing length of wear. Forty-one of the exposures were associated with mild to severe skin problems. Nine of the individuals studied were diagnosed as having histologically confirmed squamous cell carcinomas at the site of exposure. The incidence of skin cancer on the ring finger was eleven times that expected for men and forty-five times that expected for women. These data indicate that physicians who have patients with skin lesions of the ring finger should be aware of the possibility of exposure to a radioactive gold ring

  8. Measures against radioactive contamination due to Fukushima First Nuclear Power Plant accidents. Part 3. Removing and decontamination of contaminated soil

    International Nuclear Information System (INIS)

    Ishii, K.; Terakawa, A.; Matsuyama, S.

    2012-01-01

    We studied the structure of radioactive cesium distribution in soil and found the exponential dependence. This behavior could be explained theoretically. We developed a useful method to decontaminate the soil contaminated with radioactive cesium atoms. We applied our method to the contaminated school yards of elementary schools of Marumori town and decontaminated total area of about 7000 m"2. (author)

  9. Remediation Of Radioactive Contaminated Soil in Oil Fields

    International Nuclear Information System (INIS)

    Taha, A.A.; Hassib, G.M.; Ibrahim, Z.A.

    2011-01-01

    Radioactive contamination by naturally occurring radioactive materials (NORM) in evaporation pond has been evaluated. At several onshore oil field locations, the produced water is discharged to form artificial lagoons or ponds. Subsequently, the released waters drain to the ground leaving radioactive deposits associated with the soil that eventually require remedial action in accordance with radiation protection principles. The present study aims to investigate the remediation of contaminated soil in some oil fields and in this concern, two scenarios were proposed. The first scenario is studying the feasibility of using soil washing technique (a physical-chemical separation process) for removing radium-226 from the contaminated soil samples collected from an evaporating pond. The size/activity distribution analyses were carried out. The data obtained showed that almost 68 % of the investigated soil was coarse sand (≥ 300 μm), 28 % was medium and fine sand (≤300 μm and (≥75 μm) and only small fraction of 4 % was silt and clay (≤75 μm). A series of mild acids such as HCl and mild NaCl/HCl (chloride washing) were used for washing the investigated soil fractions. The obtained data showed that the coarse fraction ≥ 300 μm can be re mediated below a regulatory level of 1Bq/g. and the radium from this coarse fraction could be easily removed by screening and chloride washing. For the remediation of (≤ 300 μm and (≥ 75 μm soil fractions, a series of mild chloride washing experiments also showed that the chloride base (NaCl/HCl) was found to be potentially useful. However, there was a difficulty in achieving a low radium value in the fine (≥ 75 μm size fractions using chloride washing. The second scenario is to get rid of all contaminated soil and store it in a concrete basin through the program of radiological protection of personnel and environment. Preliminary gamma survey of contaminated soil showed that the significant area of the investigated

  10. An automatic drawing system for a report radioactive contamination check

    International Nuclear Information System (INIS)

    Saneyoshi, Keiji; Tomita, Satoru; Yoda, Isao

    2002-01-01

    An Automatic drawing system for a report of surface contamination check in a radiation controlled area has been developed. The system can print out the report applied for the format provided by the law from the raw data that is the output from measuring instruments. The task of a worker is only to insert an FD storing the data into a PC and to push a button. The system also yields contamination maps to indicate contamination points clearly. With this system the time to complete the report from the raw data could be decreased from more than two hours to 4 minutes. (author)

  11. Treatment of Uranium-Contaminated Concrete for Reducing Secondary Radioactive Waste

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Soo; Han, G. S; Park, U. K; Kim, G. N.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    A volume reduction of the concrete waste by appropriate treatment technologies will decrease the amount of waste to be disposed of and result in a reduction of the disposal cost and an enhancement of the efficiency of the disposal site. Our group has developed a decontamination process for uranium-contaminated (U-contaminated) concrete, and some experiments were performed to reduce the second radioactive waste. A decontamination process was developed to remove uranium from concrete waste. The yellow or brown colored surface of the wall brick with high concentration of uranium was removed by a chisel until the radioactivity of remaining block reached less than 1 Bq/g. The concrete waste coated with epoxy was directly burned by an oil flame, and the burned surface was then removed using the same method as the treatment of the brick. The selective mechanical removal of the concrete block reduced the amount of secondary radioactive waste. The concrete blocks without an epoxy were crushed to below 30 mm and sifted to 1 mm. When the concrete pieces larger than 1 mm were sequentially washed with a clear recycle solution and 1.0 M of nitric acid, their radioactivity reached below the limit value of uranium for self-disposal. For the concrete pieces smaller than 1 mm, a rotary washing machine and electrokinetic equipment were also used.

  12. Treatment of Uranium-Contaminated Concrete for Reducing Secondary Radioactive Waste

    International Nuclear Information System (INIS)

    Kim, Seung Soo; Han, G. S; Park, U. K; Kim, G. N.; Moon, J. K.

    2014-01-01

    A volume reduction of the concrete waste by appropriate treatment technologies will decrease the amount of waste to be disposed of and result in a reduction of the disposal cost and an enhancement of the efficiency of the disposal site. Our group has developed a decontamination process for uranium-contaminated (U-contaminated) concrete, and some experiments were performed to reduce the second radioactive waste. A decontamination process was developed to remove uranium from concrete waste. The yellow or brown colored surface of the wall brick with high concentration of uranium was removed by a chisel until the radioactivity of remaining block reached less than 1 Bq/g. The concrete waste coated with epoxy was directly burned by an oil flame, and the burned surface was then removed using the same method as the treatment of the brick. The selective mechanical removal of the concrete block reduced the amount of secondary radioactive waste. The concrete blocks without an epoxy were crushed to below 30 mm and sifted to 1 mm. When the concrete pieces larger than 1 mm were sequentially washed with a clear recycle solution and 1.0 M of nitric acid, their radioactivity reached below the limit value of uranium for self-disposal. For the concrete pieces smaller than 1 mm, a rotary washing machine and electrokinetic equipment were also used

  13. Radioactive inventories and sources for contamination of the Kara Sea

    International Nuclear Information System (INIS)

    Bradley, D.J.; Jenquin, U.P.

    1995-01-01

    The focus of this paper is on detailing the magnitudes of the sources of radionuclides that may be available, or have already been released to the Ob and Yenisey river systems. The emphasis is on the amounts of radioactivity that have been discharged to the environment in the West Siberian Basin. This are potential source terms to the Kara Sea via the Ob and Yenisey rivers. Russian estimates of what has been discharged to the Barents and Kara Seas, including direct ocean discharges, are summarized to provide some perspective on contamination of the Kara Sea. 1 fig., 3 tabs

  14. Recycling of radioactively contaminated materials: Public policy issues

    International Nuclear Information System (INIS)

    Hocking, E.K.

    1994-01-01

    Recycling radioactively contaminated materials requires varying degrees of interaction among Federal regulatory agencies such as the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA), State governments and regulators, the public, and the Department of Energy. The actions of any of these parties can elicit reactions from the other parties and will raise issues that must be addressed in order to achieve a coherent policy on recycling. The paper discusses potential actions and reactions of Federal regulatory agencies (defined as NRC and EPA), the States, and the Department and the policy issues they raise

  15. Long-run consequences of radioactive contamination in agriculture

    International Nuclear Information System (INIS)

    Eriksson, Aa.

    1983-01-01

    Three papers dealing with the effect of released radioactivity on agricultural operations are presented. The risk of the radiation from 137 Cs is estimated and compased with 90 Sr. The transport of radionuclides in the soil of the district of Malmoehus is calculated and applied to the radiation doses by oral food intake. Calculations of radiation doses by external radiation are also presented and the procedures to prevent contamination of food are disscussed. The items were treated at a public hearing on the 11th of June 1981 (G.B.)

  16. Decontamination of radioactive contaminated protective wear using dry cleaning solvent

    International Nuclear Information System (INIS)

    Muthiah, Pushpa; Chitra, S.; Paul, Biplob

    2013-01-01

    Liquid waste generated by conventional decontamination of radioactive contaminated cotton protective wear using detergent affects the chemical treatment of the plant. To reduce the generation of aqueous detergent waste, dry cleaning of cotton protective wear, highly soiled with oil and grease towards decontamination was tried with organic solvents. Mineral turpentine oil (MTO) among various other organic solvents was identified as a suitable organic solvent. As MTO leaves characteristic odour on the cloth, various commercial fragrances for the removal of the odour were tried. Application of the optimised dry cleaning solvent and commercial fragrance was adopted in plant scale operation. (author)

  17. Decontamination of radioactive metal surfaces by plasma arc gouging

    International Nuclear Information System (INIS)

    Osamu, K.; Makoto, K.; Takao, K.

    1983-01-01

    Experiments have been carried out to develop a new decontamination method that applies plasma arc gouging for removal of a thin surface layer from radioactively contaminated metallic wastes. Plasma arc gouging has been carried out on stainless steel and carbon steel pipes. The torch nozzle and gouging angle have been optimized to increase the decontamination rate. A water film is formed on the pipe surface to reduce both dust concentration in the off-gas and prevent slag particles, which are splashed up by the plasma gas, from adhering to the gouged surface. Using chromium-electroplated carbon steel pipes as samples, a decontamination factor of >10 3 is obtained after gouging to a depth of about0.5 mm in combination with ultrasonic cleaning

  18. Development of Decontamination Technology for Separating Radioactive Constituents from Contaminated Concrete Waste

    International Nuclear Information System (INIS)

    Min, B. Y.; Kim, G. N.; Lee, G. W.; Choi, W. K.; Jung, U. S.

    2010-01-01

    The large amount of contaminated concrete produced during decommissioning procedures and available decontamination. In Korea, more than more than 60 tons of concrete wastes contaminated with uranium compounds have been generated from UCP (Uranium Conversion Plant) by dismantling. A recycling or a volume reduction of the concrete wastes through the application of appropriate treatment technologies have merits from the view point of an increase in a resource recycling as well as a decrease in the amount of wastes to be disposed of resulting in a reduction of a disposal cost and an enhancement of the disposal safety. For unconditional release of building and reduction of radioactive concrete waste, mechanical methods and thermal stress methods have been selected. In the advanced countries, such as France, Japan, Germany, Sweden, and Belgium, techniques for reduction and reuse of the decommissioning concrete wastes have applied to minimize the total radioactive concrete waste volume by thermal and mechanical processes. It was found that volume reduction of contaminated concrete can be achieved by separation of the fine cement stone and coarse gravel. Typically, the contaminated layer is only 1∼10mm thick because cementitious materials are porous media, the penetration of radionuclides may occur up to several centimenters from the surface of a material. Most of the dismantled concrete wastes are slightly contaminated rather than activated. This decontamination can be accomplished during the course of a separation of the concrete wastes contaminated with radioactive materials through a thermal treatment step of the radionuclide (e.g. cesium and strontium), transportation of the radionuclide to fine aggregates through a mechanical treatment step. Concrete is a structural material which generally consists of a binder (cement), water, and aggregate. The interaction between highly charged calcium silicate hydrate (C-S-H) particles in the presence of divalent calcium

  19. Radioactive contamination of ingredients used in sweets industry

    International Nuclear Information System (INIS)

    Bodnar, Jozsef

    1988-01-01

    On the basis of samples tested in 1983-1987, the activity concentrations relative to unit dry matter are 2,5-3,5-times higher in cocoa shell than in cocoa beans, but the samples have only a small overall radioactive contamination within the total β activity, the 40 K activity ratio in cocoa beans is 72%, in cocoa shells 79%. The respective ratio of 87 Rb can be 20% in the two samples. The activity concentration contribution of 90 Sr and 137 Cs contamination in cocoa beans and cocoa shells is together 2%. The data of the samples from different locations do not show any significant differences. In samples from 1986-1987 the increase of cesium activity concentration can be observed. (author)

  20. Preparation of technical support material for radioactively contaminated land

    International Nuclear Information System (INIS)

    2000-01-01

    The UK Government is considering the introduction of a regulatory regime to address the legacy of sites that are radioactively contaminated due to historical activities. The Department of the Environment, Transport and the Regions (DETR) consulted on the principles of this regime in 1998, although no specific plans are yet in place to introduce the regime. The consultation paper envisaged that the Environment Agencies would have a major role in regulating the investigation and assessment of potentially contaminated sites and, where appropriate, their remediation. This work was commissioned by the Environment Agency, with support from DETR and SNIFFER (Scottish and Northern Ireland Forum for Environmental Research) to provide information on the techniques available allow the Environment Agencies to fulfil their envisaged regulatory requirements, and to assist DETR in the preparation of Statutory Guidance. The work was carried out by Entec UK Ltd, in conjunction with the NRPB

  1. Radioactive contamination of aquatic ecosystems following the Chernobyl accident

    International Nuclear Information System (INIS)

    Kryshev, I.I.

    1995-01-01

    The dynamics of radioactive contamination of aquatic ecosystems (1986-1990) is considered on the basis of observational data in the near and distant zones of the Chernobyl fallout (the Chernobyl Nuclear Power Plant (CNPP) cooling pond, the Pripyat River, the Dnieper reservoirs, and the Kopor inlet of the Gulf of Finland). Radionuclide accumulation in aquatic biota is analyzed. The results obtained indicate that the radioecological conditions in the water bodies under investigation were in a state of non-equilibrium over a long period of time following the Chernobyl accident. Reduction in the 137 Cs concentration proceeded slowly in most of the aquatic ecosystems. The effect of trophic levels which consisted of increased accumulation of radiocaesium by predatory fish was observed in various parts of the contaminated area. (author)

  2. Radioactivity in surface waters and its effects

    International Nuclear Information System (INIS)

    Stoeber, I.

    1987-01-01

    In consequence of the reactor accident in Chernobyl, the State Office for Water and Waste Disposal of North-Rhine Westphalia implemented immediate programmes for monitoring radioactivity in surface waters, including their sediments and organisms. Of the initially-measured radionuclides, only cesium-137, with its long half-life of 30 years, is of interest. Only trace amounts of the almost equally long-lived strontium 90 (half-life 28 years) were present in rainfall. Cs-137 is a non-natural-radionuclide, occurring solely as a by-product of nuclear installations and atomic bomb tests. Following the ban on surface testing of nuclear weapons, the Cs-137 content of surface waters had fallen significantly up to April 1986. The load due to the reactor disaster is of the same order of magnitude as that produced by atomic testing at the end of the nineteen-sixties. The paper surveys radioactive pollution of surface waters in North-Rhine Westphalia and its effects on water use, especially in regard to potable water supplies and the fish population. (orig./HSCH) [de

  3. BIOREMEDIATION OF CONTAMINATED SURFACE SOILS

    Science.gov (United States)

    Biological remediation of soils contaminated with organic chemicals is an alternative treatment technology that can often meet the goal of achieving a permanent clean-up remedy at hazardous waste sites, as encouraged by the U.S. Environmental Protection Agency (U.S. EPA) for impl...

  4. Map of radioactive contamination in mushrooms of Poland in 1991

    International Nuclear Information System (INIS)

    Mietelski, J.W.; Jasinska, M.; Kubica, B.; Kozak, K.; Macharski, P.

    1992-01-01

    Results from part of the Polish Government programme for forests radioactive contamination studies are presented. 278 samples of edible mushroom (Xerocomus badius) were analysed for radiocesium 137 Cs and 134 Cs) and 40 K using low-background gamma spectrometer with a germanium detector. Samples were collected from all districts of Poland in October 1991 by forest inspectors. In consequence maps of 137 Cs, 134 Cs and for 40 K concentration in ''Xerocomus badius'' are presented. The method of measurements is also presented. Large differences in radiocesium contamination levels are observed for various parts of the country. The higher radiocesium contamination level is observed in Czestochowa-Opole region. Maximum value for 137 Cs is equal to 157 kBq/kg d.m. and that for 134 Cs is equal to 16.3 kBq/kg d.m. The 40 K content level is nearly constant and equal to c.a. 1.3 kBq/kg d.m. Minimum values for caesium contamination were observed in the Bieszczady Mountains. The effective dose equivalent estimation due to the consumption of mushrooms is performed. The limits of ingestion amounts are calculated. (author). 15 refs, 15 figs, 6 tabs

  5. Strippable gel for decontamination of contaminated metallic surfaces

    International Nuclear Information System (INIS)

    Banerjee, D.; Sandhya, U.; Khot, S.A.; Srinivas, C.; Wattal, P.K.

    2013-01-01

    Periodic decontamination of radioactive laboratories including fume hoods, glove boxes and all surfaces used for handling, processing and transporting radioactive materials is mandatory in all nuclear installations as this reduces spread of contamination and decreases total man rem exposure. Conventionally, chemical decontaminating agents or surfactant solutions are used for this purpose. However, this approach leads to generation of large volume of secondary radioactive waste. The use of strippable gel is an attractive alternative with low secondary waste generation particularly where removal of loose or weakly fixed contamination is necessary and also when the decontaminated material are to be reused, for e.g. decontamination of fume hoods, glove boxes, transport casks, spent fuel storage racks, control rod drive transport containers etc. Literature on gel formulations is scarce and mostly in the patent form. The sustained effort on gel formulation development has resulted in a basic gel formulation. The gel is a highly viscous water-based organic polymer, particularly suitable for application on vertical surfaces including difficult to reach metallic surfaces of complex geometry and not just limited to horizontal surfaces. The gel can be easily applied on contaminated surfaces by brushing or spraying. Curing of the gel is complete within 16-24 hours under ambient conditions and can then be removed by peeling as a dry sheet. While curing, the contaminants are trapped in gel either physically or chemically depending upon the nature of the contaminant. Salient features of cured gel include that it is water soluble and can be disposed off after immobilization in cement. Decontamination performance of the gel was initially evaluated by applying it on SS planchettes contaminated with known amount of radionuclides such as Cs(I), Co(II) and Ce(III). The measured decontamination factor was found to be in the range of 50-500, lowest for Ce(III) and highest for Co

  6. General radioactive contamination of the biosphere in the Netherlands

    International Nuclear Information System (INIS)

    1980-01-01

    The Coordinating Committee for the Monitoring of Radioactive and Xenobiotic Substances (C.C.R.X.) reports the results of the radioactivity measurements in 1979. These are divided into measurements for the National Measuring Programme and Additional Measurements. The former include the analyses considered essential for an efficacious control of the radioactivity of the biosphere and are performed in air, soil, surface water, milk and in deposition on the surface of the earth. Samples of milk and grass from the surroundings of nuclear reactors have also been analysed. Additional measurements comprises orientating research for specific radionuclides which may be present in some samples, and other investigations which may procure useful information. Results of determinations of radionuclides in some fishery-products from the Dutch waters are given in view of the potential which some marine organisms have to concentrate fission products and especially activated corrosion products from nuclear installations. After a discussion of the results for the National Measuring Programme, a calculation is given of the total artificial radioactivity in the average Dutch diet in 1979 and of the total mean annual radiation dose the Dutch population received as a result of the presence of artificial radionuclides. Different methods studied to calculate the bone dose due to Sr-90 in the diet are outlined as an appendix. (Auth.)

  7. Process for affixing radioactive contamination on contaminated materials or wastes. Its application

    International Nuclear Information System (INIS)

    Aubouin, Guy; Aude, Georges; Tassigny, Christian de.

    1982-01-01

    The invention concerns a process for affixing radioactive contamination on materials or waste matter in order to ensure that the materials are transferred in complete safety or to package them when their activity is low. Under this process at least one coat of a resin polymerizable at ambient temperature, for example an epoxy resin, a polyester resin, a vinyl resin or a mixture of thermohardening resin and thermoplastic resin, is sprayed on to the contaminated material part by means of an electrostatic gun [fr

  8. Fluctuating asymmetry of shape in rodents from radioactively contaminated environments at Chernobyl

    International Nuclear Information System (INIS)

    Smith, M.H.; Novak, J.M.; Oleksyk, T.K.; Purdue, J.R.; Gashchak, S.

    2002-01-01

    In this study we addressed the question of whether levels of fluctuating symmetry (FA) were elevated in the radioactively contaminated populations compared to reference populations of an abundant rodent living in both environments: the yellow - necked mouse (Apodemus flavicollis). We used six populations of these animals from both inside the radioactively contaminated area close to the failed Chornobyl reactor in Ukraine and in reference areas with no apparent contamination by radionuclides. Twenty-four landmarks on the ventral surface of the rodent's skulls were used to calculate the amounts of FA of shape using Procrustes methods. A higher level of FA was documented for the populations in closest proximity to the failed Chornobyl Nuclear Plant. This index was significantly higher in populations from the most contaminated locations in the Chornobyl Exclusion Zone than in the reference areas. On the other hand, populations from the less contaminated areas inside the Chornobyl Exclusion Zone did not express FA values different from those in the reference populations

  9. Calibration of alpha surface contamination monitor

    International Nuclear Information System (INIS)

    Freitas, I.S.M. de; Goncalez, O.L.

    1990-01-01

    In this work, the results, as well as the methodology, of the calibration of an alpha surface contamination monitor are presented. The calibration factors are obtained by least-squares fitting with effective variance. (author)

  10. Strategies for the management of radioactively contaminated sites

    International Nuclear Information System (INIS)

    Butter, K. R.; Fellingham, L. R.; Holdroyd, S. D.; Smith-Briggs, J. L.

    1997-01-01

    The rehabilitation of radioactively contaminated land is a small but growing field of activity. Worldwide the activity has been dominated by the rehabilitation of uranium mining and milling sites and areas affected by major nuclear accidents, such as Chernobyl and Khystym. To date most of the sites in or associated with the UK have been small in scale and have generally involved natural radionuclides. However, with the decommissioning of large areas of many old nuclear industry sites and those associated with the development and production of nuclear weapons and the operations of nuclear submarines, the scale of these operations is set to rise very significantly. This paper addresses key considerations in managing the rehabilitation of radioactively contaminated sites. It illustrates their significance through examples ranging in scale from a few hectares to tens of thousands of square kilometres. The first example deals with a former waste storage and processing area at Harwell Laboratory. The second covers a risk reduction rehabilitation programme at the former British nuclear weapons test site at Maralinga in Australia. The third assesses the potential for cost-effective countermeasures to reduce aggregate doses received outside the 30 km exclusion zone around the Chernobyl nuclear reactor site

  11. Radiological assessment of radioactive contamination on private clothing

    International Nuclear Information System (INIS)

    Schartmann, F.; Thierfeldt, S.

    2003-01-01

    In the very rare, cases where private clothing of persons working in a nuclear installation are inadvertently contaminated and this contamination is not detected when leaving the facility, there may be radiological consequences for this person as well as for members of his or her family. The VGB (Technische Vereinigung der Grosskraftwerksbetreiber) in Germany has investigated in detail the spread of contamination in nuclear power plants. Part of this evaluation programme was a radiological analysis which has been carried out by Brenk Systemplanung GmbH (Aachen/Germany). The radiological analysis started with the definition of the source term. It is highly unlikely that activities of more than 5 kBq 60 Co could leave a plant undetected on the body or the clothes. Nevertheless activities up to 50 kBq and different nuclide vectors were regarded. It has been found that 60 Co is the most important contaminant. The radiological analysis focusses on two types of contamination: particles and surface contamination. The pathways by which such a contamination can lead to an exposure by external irradiation or by ingestion depend on the type of contamination and are analysed in detail. For example, a particle could be retained in pockets or other parts of clothing and may lead to prolonged external irradiation until the piece of clothing is washed. The analysis is performed on the basis of conservative to realistic assumptions. In conclusion, the analysis has shown that especially particle contamination needs to be focussed on. However, by the advanced detection equipment in German plants doses which may pose a health hazard can safely be excluded. (authors)

  12. 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

  13. Experimental study of contamination by inhalation of radioactive iodine aerosols. Biological balance

    International Nuclear Information System (INIS)

    Marble, G.

    1968-01-01

    Several articles have been published concerning research into contamination produced by inhalation of radioactive iodine aerosols in monkeys. Results dealing with the biological balance of this contamination are presented and discussed in this report. (author) [fr

  14. Radioactive releases from a thorium-contaminated site in Wayne, New Jersey

    International Nuclear Information System (INIS)

    Wang, J.; Yang, J.; Merry-Libby, P.

    1985-01-01

    Various residues and wastes from the production of thorium and rare earths from monazite ore are buried on a hillside in Wayne, New Jersey. In addition, contaminated materials (primarily soils) from nearby vicinity properties are being consolidated onto the Wayne site. The US Department of Energy plans to stabilize all the contaminated materials on an interim basis (20 years) until funding is available to remove them to another location. In order to evaluate the effectiveness of interim stabilization measures, pre-remedial action radioactive releases are compared to estimated releases under a reference stabilization option (one meter of soil cover). Two potential pathways are examined: (1) airborne radioactive gases (thoron and radon) and particulates, and (2) seepage into the near-surface groundwater. The relative reduction of releases into the air and groundwater for the reference stabilization option is analyzed using mathematical models for radioactive gas fluxes and atmospheric dispersion as well as groundwater transport and dispersion. The consequent health implications for nearby individuals and the general population are also estimated. Health effects due to radioactive releases are estimated to be insignificant

  15. Characterizing, for packaging and transport, large objects contaminated by radioactive material having a limited A2 value

    International Nuclear Information System (INIS)

    Pope, R.B.; Shappert, L.B.; Michelhaugh, R.D.; Cash, J.M.; Best, R.E.

    1998-02-01

    The International Atomic Energy Agency (IAEA) Regulations for the safe packaging and transportation of radioactive materials follow a graded approach to the requirements for both packaging and controls during transport. The concept is that, the lower the risk posed to the people and the environment by the contents, (1) the less demanding are the packaging requirements and (2) the smaller in number are the controls imposed on the transport of the material. There are likely to be a great number of situations arising in coming years when large objects, contaminated with radioactive material having unlimited A 2 values will result from various decommissioning and decontamination (D and D) activities and will then require shipment from the D and D site to a disposal site. Such situations may arise relatively frequently during the cleanup of operations involving mining, milling, feedstock, and uranium enrichment processing facilities. Because these objects are contaminated with materials having an unlimited A 2 value they present a low radiological risk to worker and public safety and to the environment during transport. However, when these radioactive materials reside on the surfaces of equipment and other large objects, where the equipment and objects themselves are not radioactive, the radioactive materials appear as surface contamination and, if the contaminated object is categorized as a surface contaminated object, it would need to be packaged for shipment according to the requirements of the Regulations for SCO. Despite this categorization, alternatives may be available which will allow these contaminants, when considered by themselves for packaging and transport, to be categorized as either (1) a limited quantity of radioactive material to be shipped in an excepted package or (2) low specific activity (LSA) materials to be shipped in an IP-1 package or possibly even shipped unpackaged. These options are discussed in this paper

  16. Studies on the remediation of environment contaminated with radioactive pollutants using the chemical separation technique

    Energy Technology Data Exchange (ETDEWEB)

    Kurotaki, Katsumi; Yonehara, Hidenori; Sahoo, S.K. [National Inst. of Radiological Sciences, Chiba (Japan); Ishii, Toshiaki [National Inst. of Radiological Sciences, Hitachinaka, Ibaraki (Japan). Lab. for Radioecology

    2001-12-01

    Remediation of soil and drinking water contaminated with radioactive nuclides is important for the mitigation of radiation exposure. Then we attempted to construct the remediation system including the dose estimation system using the chemical separation technique to remove pollutants from the environment. The information on air dose rate is important for assessment of risk from the radiation exposure. Then we measured the air dose rate and analysed the relationship between air dose rate and the contamination of soil at the area in Russia (Bryansk district) contaminated by Chernobyl Nuclear Power Plant accident. Moreover, we analysed the soil of Bryansk district on the concentration of rare earth elements, thorium and uranium and on the isotope ratio of strontium. On the other hand, we tried to develop the rapid measurement method of radioactivity of Sr-90 which is one of the dangerous radionuclides, because the method of radioactivity measurement in the literature is too time-consuming. It was reported recently that the molecules containing SH group form the covalent bond with gold atoms at the surface of gold plate and that crown ether compounds have strong affinity to strontium. Then we attempted to synthesize the crown ether containing SH group. In addition, we search the inorganic elements accumulated to special organisms of fishes and other animals in sea in order to find out new reagent for trace elements. Transition metal such as Co, Fe, Ni, Ti, V and Zn were detected from the intracellular granules in the bronchial heart of octopus. (author)

  17. Characterization of radioactive contamination inside pipes with the Pipe Explorer trademark system

    International Nuclear Information System (INIS)

    Lowry, W.

    1994-01-01

    The objective for the development of the Pipe Explorer trademark radiological characterization system is to achieve a cost effective, low risk means of characterizing gamma radioactivity on the inside surface of pipes. The unique feature of this inspection system is the use of a pneumatically inflated impermeable membrane which transports the detector into the pipe as it inverts. The membrane's internal air pressure tows the detector and tether through the pipe. This mechanism isolates the detector and its cabling from the contaminated surface, yet allows measurement of radioactive emissions which can readily penetrate the thin plastic membrane material (such as gamma and high energy beta emissions). In Phase 1, an initial survey of DOE facilities was conducted to determine the physical and radiological characteristics of piping systems. The inverting membrane deployment system was designed and extensively tested in the laboratory. A range of membrane materials was tested to evaluate their ruggedness and deployment characteristics. Two different sizes of gamma scintillation detectors were procured and tested with calibrated sources. Radiation transport modeling evaluated the measurement system's sensitivity to detector position relative to the contaminated surface, the distribution of the contamination, background gamma levels, and gamma source energy levels. In the culmination of Phase 1, a field demonstration was conducted at the Idaho National Engineering Laboratory's Idaho Chemical Processing Plant. The project is currently in transition from Phase 1 to Phase 2, where more extensive demonstrations will occur at several sites. Results to date are discussed

  18. Development of RadRob15, A Robot for Detecting Radioactive Contamination in Nuclear Medicine Departments

    Directory of Open Access Journals (Sweden)

    Shafe A.

    2016-09-01

    Full Text Available Accidental or intentional release of radioactive materials into the living or working environment may cause radioactive contamination. In nuclear medicine departments, radioactive contamination is usually due to radionuclides which emit high energy gamma photons and particles. These radionuclides have a broad range of energies and penetration capabilities. Rapid detection of radioactive contamination is very important for efficient removing of the contamination without spreading the radionuclides. A quick scan of the contaminated area helps health physicists locate the contaminated area and assess the level of activity. Studies performed in IR Iran shows that in some nuclear medicine departments, areas with relatively high levels of activity can be found. The highest contamination level was detected in corridors which are usually used by patients. To monitor radioactive contamination in nuclear medicine departments, RadRob15, a contamination detecting robot was developed in the Ionizing and Non-ionizing Radiation Protection Research Center (INIRPRC. The motor vehicle scanner and the gas radiation detector are the main components of this robot. The detection limit of this robot has enabled it to detect low levels of radioactive contamination. Our preliminary tests show that RadRob15 can be easily used in nuclear medicine departments as a device for quick surveys which identifies the presence or absence of radioactive contamination.

  19. Dry decontamination technology development for high radioactive contaminant application - Development of residual radiation assessment methodology for high radioactive facility decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Lee, G. J.; Hong, D. S.; Jeong, H. Y. [Korea Advanced Institute of Science and Technology, Taejon (Korea)

    2000-04-01

    Humidity around the concrete structure can make the moisture distribution within the concrete. Moisture content of the structure will change due to the diffusion process with time. Radioactive material on the surface of concrete will eventually diffuse into the porous concrete and contaminates the internal region of the concrete. In this study, we have assumed two different diffusion processes depending on the different moisture content. One is for slow diffusion process near the surface and the other is for fast diffusion process in deep region. We have developed the mathematical diffusion model for the two different diffusion regions and the corresponding analytic solutions for the two regions are obtained. 19 refs., 15 figs., 9 tabs. (Author)

  20. Inductively coupled plasma mass spectrometer installation modifications in a radioactive contaminated laboratory for the analysis of DOE radioactive waste streams

    International Nuclear Information System (INIS)

    Giaquinto, J.M.; Keller, J.M.; Meeks, A.M.

    1997-04-01

    The operation and maintenance of a complex analytical instrument such as an inductively coupled plasma mass spectrometer in a radioactive contaminated environment presents unique problems and challenges that have to be considered in the purchasing and installation process. Considerations such as vendor experience, typical radiation levels, sample matrices encountered during sample analysis, instrument accessibility for maintenance, and upkeep must be incorporated into the decision process. The Radioactive Materials Analytical Laboratory (RMAL) at Oak Ridge National Laboratory (ORNL) recently purchased and installed an inductively coupled plasma mass spectrometer for the analysis of Department of Energy (DOE) radioactive waste streams. This presentation will outline the purchasing decision, installation of the instrument, and how the modifications needed to operate in a radioactive contaminated laboratory do not significantly impact the daily operation and maintenance requirements of the instrument. Also, a contamination survey of the system will be presented which demonstrates the contamination levels in the instrument from the sample introduction system to the detector

  1. Inductively coupled plasma mass spectrometer installation modifications in a radioactive contaminated laboratory for the analysis of DOE radioactive waste streams

    International Nuclear Information System (INIS)

    Giaquinto, J.M.; Keller, J.M.; Meeks, A.M.

    1998-01-01

    The operation and maintenance of a complex analytical instrument such as an inductively coupled plasma mass spectrometer in a radioactive contaminated environment presents unique problems and challenges that have to be considered in the purchasing and installation process. Considerations such as vendor experience, typical radiation levels, sample matrices encountered during sample analysis, instrument accessibility for maintenance, and upkeep must be incorporated into the decision process. The Radioactive Materials Analytical Laboratory (RMAL) at Oak Ridge National Laboratory (ORNL) recently purchased and installed an inductively coupled plasma mass spectrometer for the analysis of Department of Energy (DOE) radioactive waste streams. This presentation will outline the purchasing decision, installation of the instrument, and how the modifications needed to operate in a radioactive contaminated laboratory do not significantly impact the daily operation and maintenance requirements of the instrument. Also, a contamination survey of the system will be presented which demonstrates the contamination levels in the instrument from the sample introduction system to the detector. (author)

  2. Monitoring of surface and airborne contamination

    Energy Technology Data Exchange (ETDEWEB)

    Pradeep Kumar, K S [Bhabha Atomic Research Centre, Bombay (India)

    1997-06-01

    Indian nuclear energy programme aims at total safety in all activities involved in the entire fuel cycle for the occupational workers, members of the public and the environment as a whole. Routine radiation monitoring with clearly laid out procedures are followed for ensuring the safety of workers and public. Radiation monitoring carried out for the nuclear installations comprises of process monitoring, monitoring of effluent releases and also of the radiation protection monitoring of the individuals, work place and environment. Regulations like banning of smoking and consumption of food and drink etc. reduces the risk of direct ingestion even if inadvertent spread of contamination takes place. Though limit of transportable surface contamination is prescribed, the health physicists always follow a ``clean on swipe`` philosophy which compensates any error in the measurement of surface contamination. In this paper, the following items are contained: Necessity of contamination monitoring, accuracy required in the calibration of surface contamination monitors, methodology for contamination monitoring, air monitoring, guidelines for unrestricted release of scrap materials, and problems in contamination monitoring. (G.K.)

  3. Equipment for measuring contamination of hands with radioactive material

    International Nuclear Information System (INIS)

    Erban, J.; Kleinbauer, K.; Husak, V.; Grigar, O.

    1986-01-01

    The claimed device consists of a scintillation detector mounted in a shielding case consisting of rings. The shielding case is provided with a cavity with an inlet opening lined with polyethylene foil. The cavity shape, shielding and replaceable foil guarantee minimizing the interfering effect of radiation sources in the vicinity and of contamination of the device. Gradually inserting the hand in the cavity or suitably placing the hand can locate contamination of the hand surface. The sensitivity of the device for 125 I and 99 Tc is 200-times higher than that of Geiger-Mueller counter instruments. (M.D.)

  4. Radioactive contamination in the environs of the Hanford Works for the period April - May - June, 1948

    Energy Technology Data Exchange (ETDEWEB)

    Singlevich, W.

    1948-10-15

    This report summarizes the radioactive contamination measured at the Hanford Works and immediate plant areas for the quarter April, May, and June, 1948. Topics discussed are: Meteorology; airborne contamination; contamination in the Columbia and Yakima Rivers; and contamination in rain, drinking water, vegetation, and in Hanford Wastes.

  5. Comparison between ex situ and in situ measurement methods for the assessment of radioactively contaminated land. Comparison between measurement methods for the characterisation of radioactively contaminated land

    International Nuclear Information System (INIS)

    Rostron, Peter D.; Ramsey, Michael H.; Heathcote, John A.

    2012-01-01

    In the UK, it is estimated that there may be 20,000,000 cubic metres of contaminated land at Sellafield alone. Harwell and Dounreay are known to have significant amounts of radioactive or nonradioactive contaminated land (NDA, 2006). It is therefore important to devise optimal methods for the characterisation of areas of land for radionuclide content, in order to enable cost-effective decommissioning. With chemical contaminants, ex situ measurements are made on a larger volume of soil than are in situ measurements, such as PXRF. However, the opposite is often true for the characterisation of radioactive contamination, when this involves the detection of penetrating radiation from γ-emitting radionuclides. This means that when investigating for hotspots of radioactive contamination at or near the ground surface, better coverage can be obtained using in situ methods. This leads to the question, what is the optimal strategy (e.g. percentage coverage, counting time) for in situ characterisation of radioactively contaminated land' Surveys on light-moderate contaminated areas of ground were conducted at Dounreay in order to compare the relative effectiveness of in situ and ex situ methods, both for the detection of radioactive hotspots and also for estimating the average radionuclide content of an area of ground. These surveys suggest that continuous coverage by in situ devices is more effective at hotspot detection, with ex situ laboratory measurements being less effective, although in one case elevated activity below 10 cm depth that was identified by ex situ measurement was not located by in situ measurement. The surveys also highlighted that careful choice of an appropriate spatial model is critical to the estimation of activity concentrations over averaging areas. Whereas continuous coverage may be considered necessary for hotspot identification, in the particular case of the detection of hot particles (where the particle is very small compared to the sampling

  6. Simplified model for radioactive contaminant transport: the TRANSS code

    International Nuclear Information System (INIS)

    Simmons, C.S.; Kincaid, C.T.; Reisenauer, A.E.

    1986-09-01

    A simplified ground-water transport model called TRANSS was devised to estimate the rate of migration of a decaying radionuclide that is subject to sorption governed by a linear isotherm. Transport is modeled as a contaminant mass transmitted along a collection of streamlines constituting a streamtube, which connects a source release zone with an environmental arrival zone. The probability-weighted contaminant arrival distribution along each streamline is represented by an analytical solution of the one-dimensional advection-dispersion equation with constant velocity and dispersion coefficient. The appropriate effective constant velocity for each streamline is based on the exact travel time required to traverse a streamline with a known length. An assumption used in the model to facilitate the mathematical simplification is that transverse dispersion within a streamtube is negligible. Release of contaminant from a source is described in terms of a fraction-remaining curve provided as input information. However, an option included in the code is the calculation of a fraction-remaining curve based on four specialized release models: (1) constant release rate, (2) solubility-controlled release, (3) adsorption-controlled release, and (4) diffusion-controlled release from beneath an infiltration barrier. To apply the code, a user supplies only a certain minimal number of parameters: a probability-weighted list of travel times for streamlines, a local-scale dispersion coefficient, a sorption distribution coefficient, total initial radionuclide inventory, radioactive half-life, a release model choice, and size dimensions of the source. The code is intended to provide scoping estimates of contaminant transport and does not predict the evolution of a concentration distribution in a ground-water flow field. Moreover, the required travel times along streamlines must be obtained from a prior ground-water flow simulation

  7. Occurrence of Surface Water Contaminations: An Overview

    Science.gov (United States)

    Shahabudin, M. M.; Musa, S.

    2018-04-01

    Water is a part of our life and needed by all organisms. As time goes by, the needs by human increased transforming water quality into bad conditions. Surface water contaminated in various ways which is pointed sources and non-pointed sources. Pointed sources means the source are distinguished from the source such from drains or factory but the non-pointed always occurred in mixed of elements of pollutants. This paper is reviewing the occurrence of the contaminations with effects that occurred around us. Pollutant factors from natural or anthropology factors such nutrients, pathogens, and chemical elements contributed to contaminations. Most of the effects from contaminated surface water contributed to the public health effects also to the environments.

  8. Radioactive contamination of former Semipalatinsk test site area

    International Nuclear Information System (INIS)

    Artem'ev, O.I.; Akhmetov, M.A.; Ptitskaya, L.D.

    2001-01-01

    The nuclear weapon infrastructure elimination activities and related surveys of radioactive contamination are virtually accomplished at the Semipalatinsk test site (STS). The radioecological surveys accompanied closure of tunnels which were used for underground nuclear testing at Degelen technical field and elimination of intercontinental ballistic missile silo launchers at Balapan technical field. At the same time a ground-based route survey was carried out at the Experimental Field where aboveground tests were conducted and a ground-based area survey was performed in the south of the test site where there are permanent and temporary inhabited settlements. People dwelling these settlements are mainly farmers. The paper presents basic results of radiological work conducted in the course of elimination activities. (author)

  9. Onsite disposal of radioactive waste: Estimating potential groundwater contamination

    International Nuclear Information System (INIS)

    Goode, D.J.; Neuder, S.M.; Pennifill, R.A.; Ginn, T.

    1986-11-01

    Volumes 1 and 2 of this report describe the NRC's methodology for assessing the potential public health and environmental impacts associated with onsite disposal of very low activity radioactive materials. This volume (Vol. 3) describes a general methodology for predicting potential groundwater contamination from onsite disposal. The methodology includes formulating a conceptual model, representing the conceptual model mathematically, estimating conservative parameters, and predicting receptor concentrations. Processes which must generally be considered in the methodology include infiltration, leaching of radionuclides from the waste, transport to the saturated zone, transport within the saturated zone, and withdrawal at a receptor location. A case study of shallow burial of iodine-125 illustrates application of the MOCMOD84 version of the US Geological Survey's 2-D solute transport model and a corresponding analytical solution. The appendices include a description and listing of MOCMOD84, descriptions of several analytical solution techniques, and a procedure for estimating conservative groundwater velocity values

  10. Epidemiologic studies of radioactively contaminated environments and cancer clusters

    International Nuclear Information System (INIS)

    Boice, J.D. Jr.

    1991-01-01

    This paper reports on epidemiologic studies which address the distribution and determinants of disease in human populations. Investigations of the possible adverse effects of living in radioactively contaminated environments are difficult to conduct, however, because human populations tend to be fairly mobile, cumulative exposures to individuals from environmental conditions are difficult to estimate, and the risks associated with such exposures tend to be small relative to background levels of disease. Such studies can be arbitrarily classified as geographic correlation surveys, analytic studies, and cluster evaluations. Geographic correlation studies (ecological surveys) relate disease in populations to area characteristics. Although exposure to individuals is unknown, these exploratory or hypothesis-generating studies can identify areas to target for further in-depth evaluation. Analytic investigations relate individual exposure information to disease occurrence. Unusual occurrences of disease in time and place (clusters) occasionally point to a common environmental factor; cluster evaluations have been most successful in identifying the source of infectious disease outbreaks

  11. Disposal of slightly contaminated radioactive wastes from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Minns, J.L. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-02-01

    With regard to the disposal of solid wastes, nuclear power plants basically have two options, disposal in a Part 61 licensed low-level waste site, or receive approval pursuant to 20.2002 for disposal in a manner not otherwise authorized by the NRC. Since 1981, the staff has reviewed and approved 30 requests for disposal of slightly contaminated radioactive materials pursuant to Section 20.2002 (formerly 20.302) for nuclear power plants located in non-Agreement States. NRC Agreement States have been delegated the authority for reviewing and approving such disposals (whether onsite or offsite) for nuclear power plants within their borders. This paper describes the characteristics of the waste disposed of, the review process, and the staff`s guidelines.

  12. Experiment on Physical Desalinisation of Uranium-contaminated Gravel Surface

    International Nuclear Information System (INIS)

    Park, Uk-Ryang; Kim, Gye-Nam; Kim, Seung-Soo; Han, Gyu-Seong; Moon, Jai-Kwon

    2014-01-01

    As a result, the method to wash uranium-contaminated gravels could not get satisfactory desalinization rate. During the long oxidization process it was judged that uranium penetrated inside the gravels, so we tried to increase the desalinization rate by fragmentizing them into pieces and then washing them. The desalinization rate after fragmentizing the gravels into pieces and washing them brought a satisfactory result.. However, we could obtain desired concentration for gravels with high uranium concentration by fragmentizing them and breaking them further into even smaller pieces. Likewise, desalinization using soil washing process is complicated and has to go through multiple washing steps, resulting in too much of waste fluid generated accordingly. The increase of waste fluid generated leads to the increase in by-products of the final disposal process later on, bringing a not good economic result. Furthermore, taking into account that the desalinization rate is 65% during soil washing process, it is expected that gravel washing will show a similar desalinization result; it is considered uneasy to have a perfect desalinization only by soil washing. The grinding method is actually used in the primary desalinization process in order to desalinize radioactivity-contaminated concrete. This method does desalinization by grinding the radioactivity-contaminated area of the concrete surface with desalinization equipment, which enables a near-to-perfect desalinization for relatively thinly contaminated surface. Likewise, this research verified the degree of desalinization by applying the grinding method and comparing it to the fragmentizing-washing method, and attempted to find a method to desalinize uranium-contaminated gravels more effectively. In order to desalinize uranium-contaminated gravels more effectively and compare to the existing washing-desalinization method, we conducted a desalinization experiment with grinding method that grinds gravel surface. As a

  13. Development of floor smear sampler (floor radioactive contamination measuring instrument) for nuclear facilities

    International Nuclear Information System (INIS)

    Miyagawa, Minoru; Ito, Haruo; Nozawa, Katsuro; Shinohara, Yotaro; Hashimoto, Hiroshi.

    1980-01-01

    The control of the floor contamination with radioactive substances in nuclear facilities is strictly carried out by smear method, in which the contaminants on floor surfaces are wiped off with filter papers or cloths, and the contamination density on the floor surfaces is measured through their intensity of radioactivity. This wiping work is laborious since it is carried out in leaning-over posture when many samples must be taken in wide floor area. Therefore, to achieve labor saving in this work, an automatic sampler was developed. In the floor smear sampler developed, samples are taken on long band type wiping cloths only by handle operation, and the sample numbers are printed. When many samples are taken in wide floor area, this is especially effective, and the labor saving by 1/3 to 1/2 can be achieved. At present, this sampler is put in practical use in Hamaoka Nuclear Power Station. At the time of trial manufacture, the method of wiping, the mechanisms of wiping, cloth feeding and running, the contact pressure and the number of times of wiping affecting wiping efficiency and the required torque of a motor were examined. The developed sampler is that of constant contact pressure, vibration wiping type, and the rate of sampling is 10 sec per one sample. 100 samples can be taken on one roll of wiping cloth. The results of performance test are reported. (Kako, I.)

  14. Honey As A Bioindicator Of Environmental Radioactive Contamination In Croatia

    International Nuclear Information System (INIS)

    Franic, Z.; Petrinec, B.; Marovic, G.

    2015-01-01

    Radioecological investigations regarding fission products in foodstuffs in Croatia are implemented as part of an extended and still ongoing radioactive contamination monitoring programme of the human environment. The programme has been designed and endorsed by the Croatian State Office for Radiological and Nuclear Security and fully harmonized with European legislation, i.e. the European Commission's recommendation of June 2000 on the application of Article 36 of the Euratom Treaty. For describing the overall possible impact the contaminants have on the entire region, the most efficient sampler would be one that covers the largest area possible. In this sense, honey has been shown to be an excellent biological indicator for detecting radionuclides but also other pollutants such as heavy metals. In Croatia, radiocaesium nuclides like 137Cs and 134Cs in honey were first investigated after the Chernobyl accident in 1986. For both radionuclides, the activity concentrations in honey, which peaked in May 1986, decreased exponentially and the estimated ecological residence time, corrected for radioactive decay, was found to be 1.23 y for 137Cs and 1.07 y for 134Cs. In the early 1990s, activity concentrations in honey for both radionuclides were under the detection limit, but again rose after the Fukushima Daiichi accident. Effective radiation doses due to radiocaesium, received by the Croatian population by honey consumption, even in the year of the Chernobyl accident were estimated to be very small, the per caput dose being less than 1 micro Sv. Based on radioecological investigations of honey, we argue that the mobility of honey bees and their ability to integrate all exposure pathways could add another level of confidence to the present monitoring program if honey and other bee-farming products are included in the routine radioecological monitoring programme for the Croatian environment. (author).

  15. Surface and Interface Studies with Radioactive Ions

    CERN Multimedia

    Weber, A

    2002-01-01

    Investigations on the atomic scale of magnetic surfaces and magnetic multilayers were performed by Perturbed Angular Correlation (PAC) spectroscopy. The unique combination of the Booster ISOLDE facility equipped with a UHV beamline and the UHV chamber ASPIC (Apparatus for Surface Physics and Interfaces at CERN) is ideally suited for such microscopic studies. Main advantages are the choice of problem-oriented radioactive probes and the purity of mass-separated beams. The following results were obtained: $\\,$i) Magnetic hyperfine fields (B$_{hf}$) of Se on Fe, Co, Ni surfaces were determined. The results prompted a theoretical study on the B$_{hf}$ values of the 4sp-elements in adatom position on Ni and Fe, confirming our results and predicting unexpected behaviour for the other elements. $\\,$ii) Exemplarily we have determined B$_{hf}$ values of $^{111}$Cd at many different adsorption sites on Ni surfaces. We found a strong dependence on the coordination number of the probes. With decreasing coordination nu...

  16. Measures to be taken in cases of radioactive contamination of the skin

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    This recommendation refers to those technical, medical and scientific facilities in which unsealed radioactive substances are handled. These facilities include, among other things: nuclear power plants, facilities of the fuel cycle, scientific and industrial laboratories, doctors' practices, hospitals and medical laboratories. Any unnecessary contamination of individuals shall be avoided. If contamination does occur, the resulting radiation exposure shall be kept as low as possible, even below the dose limits of the Radiological Protection Ordinance, taking into consideration the state of the art and also taking into account all circumstances pertaining to each individual case. Preventive measures to avoid or limit contamination represent the most effective form of protection. Preventive measures therefore include regular checks on the condition of the skin and constant personal skin care. Specific decontamination instructions must be provided for each individual plant and also, where applicable, for each individual workplace. Contaminated items of clothing must be removed before decontamination is commenced. Low levels of contamination can usually be eleminated in one step by washing with water. There is no need to carry out further decontamination steps where the decontamination effect is less than 10% and the remaining surface-related activity is less than 10 Bq/cm 2 (averaged over 100 cm 2 where the contamination is largely distributed over the entire area). (orig.) [de

  17. Radioactive contamination of copper produced using nuclear explosives

    Energy Technology Data Exchange (ETDEWEB)

    Crouse, D J; Arnold, W D; Hurst, F J

    1970-05-15

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

  18. Quantification of surface contamination: principles and applications

    International Nuclear Information System (INIS)

    Vo-Dinh, T.

    1982-01-01

    The applications discussed in this paper underscore the usefulness and versatility of molecular luminescence spectroscopy as an efficient surface detection technique. The technique can be used not only as a qualitative characterization method, but also as a quantitative analytical tool to detect trace contaminants on surfaces. Recent advances in instrumentation and methodology have expanded the applicability of surface luminescence into many new problem areas. Trace organics are emphasized here

  19. On-site radioactive soil contamination at the Andreeva Bay shore technical base, Northwest Russia

    NARCIS (Netherlands)

    Reistad, O.; Dowdall, M.; Selnaes, O. G.; Standring, W. J. F.; Hustveit, S.; Steenhuisen, F.; Sorlie, A.

    The radioactive waste (RAW) storage site at Andreeva Bay in the Russian Northwest has experienced radioactive contamination both as a result of activities carried out at the site and due to incidents that have occurred there in the past such as accidental releases of radioactive materials. The site

  20. NERIS workshop. Lasting contaminations and land development. After Fukushima: the possibility of a lasting radioactive contamination

    International Nuclear Information System (INIS)

    2011-11-01

    The document contains the contributions proposed during a workshop and the content of discussions after these contributions. For the first day, case studies are thus reported and commented: land contamination in Japan after the Fukushima accident, the CENTRACO plant accident, medium and long term stakes within the context of a lasting contamination by pesticides (the case of chlordecone pollution in the French West Indies), the complex and multiple actor challenges in the case of long duration radiological contamination for land agriculture, a lasting contamination in urban environment (the case of Metaleurop). The second session addressed the conditions and means for preparedness of local actors to a lasting radioactive contamination: the Norwegian approach, how to take the post-accidental perspective into account in the local safeguard plans, the PRIME project (research project on radio-ecological sensitivity indices and multi-criteria methods applied to the environment of an industrial territory), the pilot radiation protection project of the Montbeliard district, the OPAL project (to provide the local information commissions with post-accidental zoning information on the different French nuclear sites)

  1. Implementation of GIS-DSS PRANA within sustainable rehabilitation of radioactive contaminated territories

    International Nuclear Information System (INIS)

    Yatsalo, B.

    2003-01-01

    Full text: Analysis of the current situation in contaminated farms and settlements of Bryansk region is based on the monitoring data and model estimates. Model assessments of agricultural produce contamination, doses to the local population, radiological risk and results of countermeasure (CM) implementation have been carried out with the use of PRANA GIS-DSS. Applied Geographic Information System (GIS) PRANA is a Decision Support System (DSS) for implementation within the rehabilitation of radioactive contaminated territories. PRANA has been introduced for practical use in Bryansk as a GIS-DSS system for monitoring networking support and countermeasure analysis. The main blocks of the PRANA DSS are: libraries of electronic maps, including different layers of vector maps of landuse for all contaminated districts of Bryansk region: Novozybkov, Klintsy, Gordeevsky, Krasnogorsky, Zlynkovsky and Klimovsky (more than 30000 polygons of vector electronic maps); databases (radioecological, ecological, economic, demographic and other monitoring data and model parameters, including attributive information of vector electronic maps); model blocks for assessing: contamination of agricultural production, external and internal doses to the local population, radiological risks and corresponding results of CMs implementation; evaluation of CMs effectiveness and decision-making support an protection of the population and rehabilitation of radioactive contaminated territories both on local and regional/district levels (from separate settlement/field up to group of settlements/farms and region as a whole). The following 'risk indices' are considered within decision-making an Risk Based Land Management (RBLM) with the use of PRANA DSS: surface density contamination of territory with radionuclides ( 137 Cs, 90 Sr); contamination of agricultural production (plant growing and animal husbandry, including farm and private production); external and internal doses to the local population

  2. Surface temperature measurement with radioactive kryptonates

    International Nuclear Information System (INIS)

    Pruzinec, J.; Piatrik, M.

    1976-01-01

    The preparation and use of radioactive kryptonates is described for measuring surface temperatures within the region of 45 to 70 degC. Two samples each were prepared of kryptonated beechwood and hydroquinone on a paper carrier. One sample served as the standard which during the experiment was placed in a thermostat at a constant temperature of 45 degC. The second sample was placed in another thermostat where the temperature changed from 45 to 70 degC. Both samples were in the thermostat for 30 mins. The temperature was raised in steps of 2.5 degC and the time of measurement was constant in both samples. The dependences are given of the drop in activity on temperature for both types of samples. The difference was determined of the drop in activity between the standard and the second sample and the relation for measuring the temperature of the sample was determined therefrom. (J.B.)

  3. Contamination of stainless steel process piping with radioactive cobalt colloids and methods for decontamination

    International Nuclear Information System (INIS)

    Adeleye, S.A.; White, D.A.

    1992-01-01

    Significant deposits of activity can occur on the internal surface of pipework carrying aqueous radioactive liquid. This paper describes experimental work to contaminate stainless steel piping with colloidal particles of Co 60 and considers decontamination methods. The effects on steel contamination of varying cobalt concentration and aqueous liquor pH were investigated. Deposition increased with increasing cobalt concentration and the ''plate-out'' increased markedly with increasing liquid pH. Low deposition occurred at pH ∼ 2 increasing by orders of magnitude at pH ∼ 10. Steel type had an effect on activity picked up. It was shown that liquid turbulence, on the surface, reduced activity deposition. Since the extent of contamination to be removed depends on deposition or ''plate-out'' kinetics, the factors affecting the rate of activity deposition are considered. Specimens of steel piping were treated by contacting with acid, electroetching or abrasion with emery cloth. Surface treatment was shown to delay deposition, in certain instances, but did not have much effect on overall equilibrium level of surface activity. The surface activity could be reduced by treatment with dilute nitric acid: however significant activity remained. Most of the remaining activity could be removed by treatment with nitric acid in an ultrasonic bath. (Author)

  4. Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land.

    Science.gov (United States)

    Nancarrow, D J; White, M M

    2004-03-01

    A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950,000 m3). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

  5. Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land

    International Nuclear Information System (INIS)

    Nancarrow, D J; White, M M

    2004-01-01

    A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950 000 m 3 ). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

  6. Early-Stage Bioassay for Monitoring Radioactive Contamination in Living Livestock

    OpenAIRE

    Yamaguchi, Toshiro; Sawano, Kaita; Kishimoto, Miori; Furuhama, Kazuhisa; Yamada, Kazutaka

    2012-01-01

    Soil samples from the ground surface and feces and blood from a mixed-breed male pig were collected on April 10, 2011 at a farm within 20 km of the Fukushima Daiichi nuclear power plant. The radioactivity of each sample was measured using a Ge semiconductor detector. Despite the fact that the pig had been fed non-contaminated imported feed, 131I, 134Cs and 137Cs were detected in the feces, and 134Cs and 137Cs were detected in the blood clots. Because it is considerably difficult to measure ra...

  7. Survey of radioactive contamination distribution in the Naka-Dori area, Tohoku, Japan

    International Nuclear Information System (INIS)

    Hohara, Sin-ya; Inagaki, Masayo; Yamanishi, Hirokuni; Wakabayashi, Genichiro; Sugiyama, Wataru; Itoh, Tetsuo

    2013-01-01

    The Kinki University Atomic Energy Research Institute investigated radioactive contamination due to the Fukushima Daiichi Nuclear Power Plant accident in urban areas of the Fukushima Naka-Dori Area in the TOHOKU region, Japan. A specific activity measurement of the surface soil and a survey of the dose rate distribution in urban areas were performed. From the results of this research, a decrease in dose rate in paved areas became clear, and differences due to the “wash out effect” in paved areas for different paving materials was measured and verified. (author)

  8. Sanitation of conditioned radioactive waste after a contamination accident

    International Nuclear Information System (INIS)

    Aeppli, J.

    1980-01-01

    In June 1978, there occurred in the port of Ijmuiden, Netherlands, a contamination incident involving drums originating from Switzerkand and containing radioactive wastes intended to be dumped into the sea. The batch of 207 drums excluded from the sea-dumping action had to be sanitated for the next year dumping in such a manner, that these wastes met the international requirements and could be disposed of by sinking them into the Atlantic. As a consequence of extensive sanitation work, requiring part of the wastes to be newly conditioned and several drums to be packaged again, the total weight of the wastes ready for dumping was doubled. The total radiation exposure for the personnel that took part in the individual phases of sanitation amounted to about 10 man-rem. The main causes for this contamination incident were unusual chemical composition of the concentrate to be solidified, unsufficient quality control and a position not suitabble for transport. The measures taken after this incident intend to avoid similar occurrences in the future. (orig.) [de

  9. Soil contamination. part 1. changes in the humidity of non saturated soils after reject in a limited space. part 2. movements of radioactive ions in non saturated soils after reject in a limited space; Contamination des sols (1. partie). Evolution de l'humidite dans les sols non satures apres rejets sur une surface limitee. (2. partie). Comportement des ions radioactifs dans les sols non satures apres rejets d'eau sur une surface limitee

    Energy Technology Data Exchange (ETDEWEB)

    Rancon, D [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1972-07-01

    An important feature in radiological safety studies of sites is the knowledge of water movements in the unsaturated layer surmounting aquifer; this zone of aerated soil can be effective as a protection against aquifer contamination. Utilizing a neutron-moisture meter, a method was developed permitting to build graphically the hydric states of soil and the moistened volume evolution with time in the particular case of a limited feeding surface. It is also possible to measure moisture gradients, drying kinetics, the retention capacity of soil and the gravific water content achieved by a given water head. The initial hydric state has an effect only upon the infiltration rate and neither upon the moistened front position nor upon the volume of moistened soil; consequently, the storable water amount in soil can be calculated. When water feeding has been stopped, the volume of moistened soil increases to an equilibrium state restricted by the moistened front and all the other water movements occur exclusively inside this volume. Consequently in case of radioactive waste disposal, the ionic pollution will be confined inside a measurable volume, the moistened front being the maximum limits of this volume. Part 2. Following up the report on water movements in non-saturated s o i l s after reject on a limited space - CEA R 3635 (1) - the radioactive ions movements in these soils are studied in using an anion and a cation of reference: iodine 131 and strontium 85. The experimental method is founded on the simultaneous measurements of moisture and radioactivity fronts by means of a neutrons moisture meter and an specially conceived radioactivity probe. It has so been possible to measure: the relative velocities of moisture and radioactivity fronts; the contaminated soil volume inside the moistened oil volume; the concentration gradients; the contamination changes upon watering; the effect of chemical composition of water upon this ions movements and the effect of soil moisture

  10. Radioactive Contamination Tenacity on Building Substrate – 17417

    Energy Technology Data Exchange (ETDEWEB)

    Demmer, Rick; Boxall, Colin

    2017-01-01

    Radiological decontamination is an essential enterprise that has become more important over the last four decades due to unfortunate accidents and the threat of terrorist actions. Decontamination can be an effective, beneficial alternative for the cleanup of radiological contamination events; however, the costs and benefits need to be balanced against those for complete removal and demolition of contaminated areas or facilities. Demolition and removal are often the first options considered in such circumstances as decontamination may be thought of as slow and costly. Decontamination has advantages, including significant waste reduction over demolition. In areas with buildings of cultural or societal importance, demolition may not be an option. Three decontamination evaluation test series are the focus of this article: SIMCON 1 and 2 (i.e., simulated contamination), and Urban RDD (radiological dispersal device, i.e., a dirty bomb detonation). These test series revealed that different contaminants respond differently during decontamination. This was found to be true with both SIMCON and Urban RDD simulant tests. SIMCON 2 especially demonstrated that chemically different contaminants respond differently to different decontamination methods: cesium appears to be less tenacious (more easily removed) than zirconium using chemical methods. These differences were underscored by the Urban RDD tests where americium and cobalt tended to precipitate on high pH surfaces (such as concrete), making them easier to remove, while cesium and strontium were essentially unaffected by surface pH and were imbibed more strongly into the substrate pore structure. While authorities argue over the contributions of contaminant chemistry and substrate morphology, the clear answer is that each has a contribution to the tenacity of a contaminant. Knowing how these characteristics interact will make us better at decontamination in the field. This knowledge refutes the efforts of perhaps well

  11. Development of maintenance procedure for plate type heat exchanger taking into account preventing radioactive contamination

    International Nuclear Information System (INIS)

    Terai, Kensuke; Someki, Hiroyuki; Ueda, Yuya

    2017-01-01

    In Japanese pressurized water reactors (PWR), heat loads of spent fuel pools (SFP) is increasing due to rising spent fuels and use of mixed oxide (MOX) fuels. Therefore, SFP cooling capacities are necessary to be enhanced, and replacement of SFP coolers or installation of additional coolers is needed. On the other hand, installation spaces of SFP coolers are limited in existing buildings. Therefore, plate type heat exchangers which can be designed to be compact because of the high heat efficiency have often been adopted for SFP coolers instead of shell and tube type heat exchangers in general use. Plate type heat exchangers have to be overhauled periodically for inspection and gasket replacement. However, in plate type SFP coolers, radioactive SFP water and non-radioactive component cooling water (CCW) alternately run through between each plate. Thus there is a concern that the CCW system may be contaminated by radioactive materials from the SFP water during overhaul of the SFP cooler. In order to solve this problem, we have developed the maintenance procedure of the plate type SFP coolers to prevent CCW side contamination by coating the contaminated surfaces with strippable paint prior to disassembly. Before applying this developed maintenance procedure to actual equipment, we have performed the following verification tests. (1) Confirmation of fundamental characteristics for strippable paint. Firstly, we selected both water-based and solvent-based strippable paints. Secondly, we tested and confirmed the detachability and the drying time of the selected strippable paints respectively. Moreover we also confirmed that the selected strippable paints are appropriate materials from the viewpoint of chemical composition restriction of consumable materials used in nuclear power plant. (2) Confirmation of workability for paint filling, drying and peeling off. The strippable paints need to be peeled off after filling into plate type heat exchanger and draining

  12. Secondary radioactive contamination of the Black Sea after Chernobyl accident: recent levels, pathways and trends

    International Nuclear Information System (INIS)

    Gulin, S.B.; Mirzoyeva, N.Yu.; Egorov, V.N.; Polikarpov, G.G.; Sidorov, I.G.; Proskurnin, V.Yu.

    2013-01-01

    The recent radionuclide measurements have showed that concentrations of the Chernobyl-derived 137 Cs and 90 Sr in the surface Black Sea waters are still relatively high, reaching 56 and 32 Bq m −3 , respectively. This is comparable or even exceeds the pre-Chernobyl levels (∼16 Bq 137 Cs and 22 Bq 90 Sr per m 3 as the basin-wide average values). The measurements have revealed that the Black Sea continues to receive Chernobyl radionuclides, particularly 90 Sr, by the runoff from the Dnieper River. An additional source of 90 Sr and 137 Cs was found in the area adjacent to the Kerch Strait that connects the Black Sea and the Sea of Azov. This may be caused by the inflow of the contaminated Dnieper waters, which come to this area through the North-Crimean Canal. The long-term monitoring of 137 Cs and 90 Sr concentration in the Black Sea surface waters and in the benthic brown seaweed Cystoseira sp., in comparison with the earlier published sediment records of the radionuclides, have showed signs of a secondary radioactive contamination, which has started to increase since the late 1990's. This may be the result of the combined effect of a higher input of radionuclides from the rivers in 1995–1999 due to an increased runoff; and a slow transport of the particulate bound radionuclides from the watersheds followed by their desorption in seawater from the riverine suspended matter and remobilization from the sediments adjacent to the river mouths. -- Highlights: • Concentration of 137 Cs and 90 Sr in the Black Sea water is still relatively high. • The Black Sea continues to receive considerable radionuclide amount from the rivers. • The North-Crimean Canal is significant source of the Black Sea radioactivity. • Secondary radioactive contamination of the Black Sea increased in the late 1990's. • Radionuclide remobilization from sediments leads to a further Black Sea pollution

  13. Development of automatic smear testing sampler for radioactive contamination of floor in nuclear power plant

    International Nuclear Information System (INIS)

    Nozawa, Katsuro; Hashimoto, Hiroshi; Shinohara, Yohtaro; Iwaki, Kiyotaka

    1980-01-01

    The floor contamination with radioactive substances in the controlled area of nuclear power stations is strictly controlled, and it is tested by the smear method, wiping the contaminants on floors with filter papers or cloths and measuring the radioactive intensity to obtain contamination density. The works are very laborious, therefore the automatic smear sampler was developed. Simple operation, shortening of time required for wiping, constant and high efficiency of wiping, and easy numbering of samples were the aims in the development. The method of wiping, the mechanisms of wiping, cloth feeding and running, the surface pressure at the time of wiping, the number of times of wiping and required motor torque were studied. The outline of the developed sampler is explained. The performance of the sampler was compared with manual wiping. The efficiency of wiping with the sampler was 92%, assuming manual wiping as 100. Difference was not observed between careful manual wiping and the wiping with the sampler, therefore it was confirmed that this automatic floor smear sampler can be put in practical use. By conventional manual sampling, the maximum limit was about 400 samples/man-day, but when this sampler is used, about 1000 samples/sampler-day is possible. At present, this sampler is operated in Hamaoka Nuclear Power Station. (Kako, I.)

  14. Status of foreign practices for the management of alpha-contaminated radioactive wastes

    International Nuclear Information System (INIS)

    Lakey, L.T.

    1982-08-01

    Alpha-contaminated radioactive wastes, a product of mixed-oxide fuel fabrication, fuel reprocessing, weapons production and decommissioning programs, are being generated in at least ten countries. There is general agreement worldwide that these wastes should be treated differently than the beta-gamma or low-level waste. There is no consensus, however, on a quantitative definition of alpha-contaminated wastes. Reported definitions vary from > 0.035 nCi/g to > 100 nCi/g. Incineration is the most common treatment, with cement and bitumen the most common fixation agents. The only disposal means in use today are the sea dumping practice by Belgium and the United Kingdom and the surface disposal and deep-well discharge by the USSR. Sea dumping, however, is restricted to low levels of alpha activity, while the USSR appears to be favoring geologic disposal. All countries appear to be moving toward deep geologic repositories as the favored means of disposing of alpha-contaminated radioactive wastes. West Germany has actually disposed of such wastes in the Asse Salt Mine but has discontinued that operation for political reasons. Repository projects are actively under way in Belgium, West Germany, India, Sweden, and the Unted States, with many other countries planning repository programs. One US project, the Waste Isolation Pilot Plant, will, according to present schedules, be the first repository operational since Asse. 6 tables

  15. Proposal of traceability chain for direct measurements of radioactive contamination in Cuba

    International Nuclear Information System (INIS)

    Walwyn Salas, Gonzalo; Tamayo Garcia, Jose A.; Cornejo Diaz, Nestor

    2008-01-01

    The measurements of the radioactive surface contamination are common used to demonstrate the compliance with safety regulations at national level. It is mandatory that those measurements are traceable to national standards through the suitable calibration of the monitors used for survey. In Cuba, there is not a harmonized methodology for evaluation of contamination from direct measurements and no standardized calibration service for portable monitors is routinely provided to users. The Secondary Standard Dosimetry Laboratory of Cuba has recently established the calibration service of contamination monitors in terms of instrument efficiency using the reference sources of known emission rate per unit area in accordance with international normative ISO 8769. In the present paper, is proposed a traceable scheme of direct measurements of contamination that involve the calibration at the laboratory level using multi-source method and the evaluation of contaminations at user level in terms of activity per unit area. Some improvements from the previous single-source method of calibration are explained in order to support the advantages that offer the new chain for those measurements in the country. (author)

  16. Radiative Transfer Model for Contaminated Rough Surfaces

    Science.gov (United States)

    2013-02-01

    reflectance of potassium chlorate and ammonium nitrate contaminated surfaces in mid-wavelength and long-wavelength infrared for detection. Our framework...obtained excellent or good results for lab measurements of potassium chlorate on most aluminum surfaces; however, ammonium nitrate on painted aluminum...misidentify potassium chlorate as ammonium nitrate and vice versa). We also observed moderate success on field data. 15. SUBJECT TERMS radiative

  17. Contamination of optical surfaces in Earth orbit

    Science.gov (United States)

    Kinser, Donald L.; Weller, Robert A.; Mendenhall, M. H.; Wiedlocher, D. E.; Nichols, R.; Tucker, D.; Whitaker, A.

    1992-01-01

    Glass and glass ceramic samples exposed to the low earth orbit environment for approximately 5.5 years on the Long Duration Exposure Facility (LDEF) were found to display limited degradation in optical transmission. Commercial optical quality fused silica samples display decreases in transmission in the 200 to 400 nm wavelength region, and this degradation appears to be a consequence of surface contamination. The contamination, found only on internal surfaces of samples, was measured by medium energy backscattering spectrometry and found to be primarily carbon. Additional thin film contamination by a species with atomic mass near 64, which was present at the level of about 8 x 10 exp 14/sq. cm has not been identified. These observations are consistent with the interpretation that organic binders used in the black absorbing paint (Chem Glaze Z-306) inside the sample holding tray were concentrated in the vicinity of the samples and photolytically cracked by solar UV radiation. The resulting decomposition products were deposited on the interior sample surface and gave rise to the optical transmission loss. No detectable contamination was observed on the external or space exposed surface of the samples. No measurable damage was detected which could be attributed to the direct action of gamma or UV radiation on the glass samples. These results emphasize the need for special precautions in the preparation of spacecraft carrying precision optical components on long duration missions.

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  19. Radioecological conditions in the towns, where the status of radioactive contamination zones will change

    International Nuclear Information System (INIS)

    Ageeva, T.N.; Shapsheeva, T.P.; Zajtsev, A.A.; Makarevich, I.A.

    2015-01-01

    The article presents data of changes in the density of soil contamination in settlements where in 2015 change of the status of contaminated areas is possible. Article contains analysis of monitoring of radioactive contamination of food from private farms, the results of radio ecological inspection conducted in 2013-2014. (authors)

  20. Studies on the radioactive contamination due to nuclear detonations II. Preliminary findings on the radioactive fallout due to nuclear detonations

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-11-25

    Since we have detected a considerable amount of artificial radioactivity in the rain in spring 1954, it has become one of the most important items, from the health physics point of view, to continue measurements of radioactivity in the rain and in the atmosphere. To watch out the radioactive contamination of our environment due to repeated nuclear weapons testings in other countries was also considered to be important from the nuclear engineering point of view, in the sense that the permissible allowances of the radioactivity for the peaceful uses of atomic energy might be lowered if the degree of radioactive contamination due to nuclear testings should continue to increase gradually and indefinitely. If the permissible level were lowered, the cost for radiation protection may be expected to increase at the peaceful uses of atomic energy and should the radioactive contamination increase seriously in the future, it was anticipated that we may have to face a very difficult situation in designing the atomic energy facilities for peaceful purposes in our country. From these points of views, we have been continuing measurements of the radioactivity in the rain in Osaka, Japan since the spring of 1954. Some of the preliminary findings are introduced in this paper.

  1. Studies on the radioactive contamination due to nuclear detonations II. Preliminary findings on the radioactive fallout due to nuclear detonations

    International Nuclear Information System (INIS)

    Nishiwaki, Yasushi

    1961-01-01

    Since we have detected a considerable amount of artificial radioactivity in the rain in spring 1954, it has become one of the most important items, from the health physics point of view, to continue measurements of radioactivity in the rain and in the atmosphere. To watch out the radioactive contamination of our environment due to repeated nuclear weapons testings in other countries was also considered to be important from the nuclear engineering point of view, in the sense that the permissible allowances of the radioactivity for the peaceful uses of atomic energy might be lowered if the degree of radioactive contamination due to nuclear testings should continue to increase gradually and indefinitely. If the permissible level were lowered, the cost for radiation protection may be expected to increase at the peaceful uses of atomic energy and should the radioactive contamination increase seriously in the future, it was anticipated that we may have to face a very difficult situation in designing the atomic energy facilities for peaceful purposes in our country. From these points of views, we have been continuing measurements of the radioactivity in the rain in Osaka, Japan since the spring of 1954. Some of the preliminary findings are introduced in this paper

  2. The iron waste from thermal power plant (t.p.p.) as the source of radioactive contamination

    International Nuclear Information System (INIS)

    Kovacevic, M.; Todorovic, D.; Radenkovic, M.; Joksic, J.; Vukcevic, M.

    2006-01-01

    The radioactivity control of the iron waste (tubes) raised from the regular maintenance of the Gacko thermo power plant has shown the allocated spots of relatively high surface contamination, mainly beta, and no enhanced levels of absorbed radiation dose in the air. Further laboratory examination of the contaminated tube samples (10- 15 cm length) determined the level and source of contamination. Gamma spectrometry (H.P. Ge, efficiency 23%) has shown the presence of 210 Pb isotope, beta-emitting radionuclide with 47 keV X-ray emission, the member of the 238 U series. The surface contamination and concentration values, determined after samples dissolution in mineral acids, are 2.4 Bq/cm 2 and 0.6 Bq/g, respectively. The radioactivity of the tubes originate from the naturally occurring radionuclides in coal, with 210 Pb activities mostly within 0.01-0.05 Bq/g. During the T.P.P. work, radioactivity is deposed with ash, flying ash and slag and partly released into atmosphere. But, the part of radioactivity is deposited at the tubes and cauldron with gases emanated during the coal combustion. In this way, the iron becomes contaminated by the natural radionuclide during the technological process. Since there are no legislative stipulations about such cases, we have applied the international recommendations saying that dose limit should not be higher than 10 Micro Sv/year for individuals. On this basis T.E.C.D.O.C. 855 define different use of metals contaminated with natural or man-made radionuclides. According this document the contaminated iron with activity lower than 0.7 Bq/g may be further processed in the steel works that is the case with the iron waste produced in the T.P.P. Gacko. (authors)

  3. use of the RESRAD-BUILD code to calculate building surface contamination limits

    International Nuclear Information System (INIS)

    Faillace, E.R.; LePoire, D.; Yu, C.

    1996-01-01

    Surface contamination limits in buildings were calculated for 226 Ra, 230 Th, 232 Th, and natural uranium on the basis of 1 mSv y -1 (100 mrem y -1 ) dose limit. The RESRAD-BUILD computer code was used to calculate these limits for two scenarios: building occupancy and building renovation. RESRAD-BUILD is a pathway analysis model designed to evaluate the potential radiological dose incurred by individuals working or living inside a building contaminated with radioactive material. Six exposure pathways are considered in the RESRAD-BUILD code: (1) external exposure directly from the source; (2) external exposure from materials deposited on the floor; (3) external exposure due to air submersion; (4) inhalation of airborne radioactive particles; (5) inhalation of aerosol indoor radon progeny; and (6) inadvertent ingestion of radioactive material, either directly from the sources or from materials deposited on the surfaces. The code models point, line, area, and volume sources and calculates the effects of radiation shielding, building ventilation, and ingrowth of radioactive decay products. A sensitivity analysis was performed to determine how variations in input parameters would affect the surface contamination limits. In most cases considered, inhalation of airborne radioactive particles was the primary exposure pathway. However, the direct external exposure contribution from surfaces contaminated with 226 Ra was in some cases the dominant pathway for building occupancy depending on the room size, ventilation rates, and surface release fractions. The surface contamination limits are most restrictive for 232 Th, followed by 230 Th, natural uranium, and 226 Ra. The results are compared with the surface contamination limits in the Nuclear Regulatory Commission's Regulatory Guide 1.86, which are most restrictive for 226 Ra and 230 Th, followed by 232 Th, and are least restrictive for natural uranium

  4. Plant protection under conditions of radioactive contamination of agricultural lands

    International Nuclear Information System (INIS)

    Filipas, A.S.; Oulianenko, L.N.; Pimenov, E.P.

    1995-01-01

    Increasing influence of anthropogenic contaminants as well as substantiated risk of the action of ionizing radiation on agroecosystems suggest the necessity of studying both the state of separate components of cenosis and search for methods on retention of ecosystem stability as a whole. In this case it should be taken into account that by retention of resistance of living organisms to the action of stress agents not only genetically conditioned potential but induction of protective reactions at the expense of ecogene action is of deciding significance as well. Protection of agricultural plants on the territories subjected to radioactive contamination resulting from the ChNPP accident brings attention of research works to a series of problems, the main one being the minimization of pesticide use by the total ecologization of technological processes, in plant growing. But an ordinary discontinuance of conducting protective chemical measures leads to growth in the number of harmful organisms in crop sowings and as a consequence an increase of crop loss and decrease of its quality. It is possible to solve this problem by introduction of measures increasing the resistance of agricultural plants to the action of unfavorable factors of environment. Application of biologically active substances (BAS) of natural and synthetic nature for incrustation of seeds fits into these methods. For the territories with increased content of radionuclides and especially by their rehabilitation the methods of preventive treatments directed to retarding the development of harmful organisms in crop sowings and excluding subsequent technological operations on chemical protection of sowings takes on special significance as it is directly connected with the problem of radiation burden on workers of agroindustrial complex

  5. Radioactive contamination: what actions for the polluted sites

    International Nuclear Information System (INIS)

    Lacoste, A.C.; Averous, J.; Palut-Laurent, O.; Dupuis, M.C.; Paquot, A.; Barescut, J.C.; Cessac, B.; Darmendrail, D.; Grevoz, A.

    2004-01-01

    A national conference was held on May, 2004, in Paris. It concerned the radioactively polluted soil and sites, in order to identify action strategies for the treatment of radioactive pollution. Several aspects have been studied: action plan for radioactivity polluted sites, regulation of radioactively polluted sites in France, situation and practice abroad, natural radioactivity and radioactive pollution: definition and limits, inventory and descriptive data on polluted sites in France and in Europe, radioactive waste and radioactivity polluted sites management: national inventory contribution, then ended with three panels sessions about experience feedback on the management of radioactively polluted sites, responsibilities, legal and regulatory context and financing issues, from evaluation to remediation for polluted sites. (N.C.)

  6. A feasibility study for decision-making support of a radioactive contamination model in an urban environment (METRO-K)

    International Nuclear Information System (INIS)

    Hwang, Won Tae; Han, Moon Hee; Jeong, Hyo Joon; Kim, Eun Han; Lee, Chang Woo

    2008-01-01

    A Korean urban contamination model METRO-K (Model for Estimates the Transient behavior of RadiOactive materials in the Korean urban environment), which is capable of calculating the exposure doses resulting from radioactive contamination in an urban environment, is taking part in a model testing program EMRAS (Environmental Modelling for RAdiation Safety) organized by the IAEA (International Atomic Energy Agency). For radioactive contamination scenarios of Pripyat districts and a hypothetical RDD (Radiological Dispersal Device), the predicted results using METRO-K were submitted to the EMRAS's urban contamination working group. In this paper, the predicted results for the contamination scenarios of a pripyat district were shown in case of both without remediation measures and with ones. Comparing with the predicted results of the models that have taken part in EMRAS program, a feasibility for decision-making support of METRO-K was investigated. As a predicted result of METRO-K, to take immediately remediation measures following a radioactive contamination, if possible, might be one of the best ways to reduce exposure dose. It was found that the discrepancies of predicted results among the models are resulted from 1) modeling approaches and applied parameter values, 2) exposure pathways which are considered in models, 3) assumptions of assessor such as contamination surfaces which might affect to an exposure receptor and their sizes, 4) parameter values which are related with remediation measures applied through literature survey. It was identified that a Korean urban contamination model METRO-K is a useful tool for decision-making support through the participation of EMRAS program

  7. Levels and trends of radioactive contaminants in the Greenland environment

    DEFF Research Database (Denmark)

    Dahlgaard, H.; Eriksson, M.; Nielsen, S.P.

    2004-01-01

    . The concentrations are expected to increase in the future, especially in East Greenland. The Bylot Sound at the Thule Airbase (Pituffik) in North-West Greenland was contaminated with plutonium and enriched uranium in a weapons accident in 1968. Biological activity has mixed accident plutonium efficiently...... into the new sediments resulting in continued high surface sediment concentrations three decades after the accident. Transfer of plutonium to benthic biota is low-and lower than observed in the Irish Sea. This is supposed to be caused by the physico-chemical form of the accident plutonium. A recent study...

  8. A prospect of the administration against problems of environmental contamination caused by radioactive nuclides

    International Nuclear Information System (INIS)

    Osako, Masahiro

    2012-01-01

    At first, focusing on the problem of radioactive contaminated wastes caused by Fukushima Daiichi Nuclear Accident, the Author described an outline of the waste management policy based on the law on special measures against the environmental contamination by radioactive nuclides. Next, the Author discussed a prospect of the environmental administration against the radioactive contamination problem. The most important mission of the environmental administration for the future must be to establish a social basis for the sustainable development, in other words the building-up of a newly social value added, through the measures against this unprecedented disaster. (author)

  9. Multiple containment for LSA [low specific activity] and SCO [surface contaminated objects] wastes

    International Nuclear Information System (INIS)

    Burgess, M.H.

    1993-09-01

    Radioactive wastes are generally transported in the form of Low Specific Activity (LSA) materials or Surface Contaminated Objects (SCO). This report proposes that a method of acknowledging the beneficial effects of multiple containment for such wastes should be written into the 1996 Edition of the IAEA Transport Regulations. Experience used to assess risks from on-site movements of radioactive material in the UK can be applied to develop safety arguments justifying the alleviation of off-site transport risks. (UK)

  10. Radioactive contamination of Bunodosoma caissarum under controlled conditions

    International Nuclear Information System (INIS)

    Santos Gouvea, R. de C. dos; Santos, P.L. dos

    The kinetics of uptake and release of radionuclides 137 Cs, 131 I, 133 Ba, 51 Cr (III and VI), 60 Co and 65 Zn in the 'cnidaria' Bunodosoma caissarum have been studied. This is an exclusively Brazilian species and easily collected on the Rio de Janeiro coastal waters. The kinetic experiments have been made in aquariums of 1000 cm 3 , in laboratory under controlled conditions and accompanied by single channel radiometry. The velocities of concentration were evident to radionuclides 131 I and 133 Ba. The larger concentration factors were registred to 51 Cr (III), 65 Zn and 51 Cr (VI), with middle values of 20,0 , 14,5 and 8,6 respectively. The same radionuclides stood out in the loss experiments, presenting the following biological half-lives : 292,2 h ( 51 Cr-III), 784,0 h ( 51 Cr-VI) and 823,0 h ( 65 Zn). This expressive value for the 65 Zn suggests a probable biological integration of this radionuclide by the species studied. The results allow us to indicate the 'anthozoa' Bunodosoma caissarum as a bioindicator of the radioactive contamination of the marine environment. (Author) [pt

  11. 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)

  12. Structure and dimensions of radioactive contamination caused by use of nuclear weapons

    International Nuclear Information System (INIS)

    Ilijas, B.

    1996-01-01

    Radioactive contamination is one of unavoidable consequences of nuclear burst. Its structure and dimensions are depended of many factors connected with type of weapon, with meteorological conditions and location of burst and characteristics of area involved. Contamination manifests in two ways - as induced radioactivity in the nearness of the center of explosion and as radioactive fallout. Induced radioactivity originates from interaction of neutrons from primary beam with elements naturally presents in environment, which results in creating radionuclides and area of radioactive contamination. Radioactive fallout consists of material formed or collected in the explosion that falls on earth in form of small particles. This contaminant contains α, β and γ sources with structure dependent of explosive energy and location of burst. Some radionuclides, often present in fallout, are very dangerous as internal sources ( 90 Sr, 131 I, 137 Cs, 239 Pu). Dimension of contaminated area varies widely, but if one has Knowledge of enough parameters, it is possible to predict its shape, as well as dose rate on some distance from zero point. Preciseness of this work is essentially affected by credibility of data involved and by kind of selected model. Using of well-chosen model enables on-time evaluation of risk from radioactive contamination and planning adequate protection. (author)

  13. Radiobiological significance of radioactive contamination - summary assessment based on great number of measurements

    International Nuclear Information System (INIS)

    Angelov, V.; Bonchev, Ts.; Mavrodiev, V.; Kyrdzhilov, N.

    1995-01-01

    In order to facilitate quantitative and qualitative characterisation of radioactive contamination the authors introduce a relative estimate of radionuclide activity by setting as a reference the most abundant element -Co-60 in the case of the Kozloduy NPP. The ratio η i of the mean annual permissible concentration in air for each radionuclide (RPC-92) to that of Co-60 is calculated. It is found that η i has the same or close values for groups of radionuclides, e.g. η i = 2.10 -4 for 238 Pu, 239 Pu, 240 Pu, 241 Am, 244 Cm; η i = 5 for 89 Sr, 91 Y; 93 Nb, 134 Cs, 137 Cs; η i = 50 for 55 Fe, 63 Ni, 95 Zr, 95 Nb, 140 Ba, 140 La. Then it is compared to the experimentally measured values of the same quantity η iexp , derived from surface contamination data. The ratio η iexp /η i is plotted against log η i . The resulting nomograms give graphic representation of the radiobiological significance of various radionuclide groups. Data from different locations at the Kozloduy NPP are presented. It is found that the alpha emitter contamination has highest values in the Unit 1 (WWER-440) control rooms after repair. The Unit 5 (WWER-1000) has lower alpha contamination compared to WWER-440 units. 1 ref., 5 figs., 1 tab

  14. Influence of radioactive contamination to agricultural products by rainfall during a nuclear accident

    International Nuclear Information System (INIS)

    Hwang, W. T.; Han, M. H.; Choi, Y. H.; Lee, H. S.; Lee, C. W.

    2001-01-01

    For the consideration of the effects on radioactive contamination of agricultural products by rainfall during a nuclear accident, the wet interception coefficients for the plants were derived, and the previous dynamic food chain model was also modified. From the results, radioactive contamination of agricultural products was greatly decreased by rainfall, and it decreased dramatically according to increase of rainfall amount. It means that the predictive contamination in agricultural products using the previous dynamic food chain model, in which dry interception to the plants is only considered, can be overestimated. Influence of rainfall on the contamination of agricultural products was the most sensitive for 131 I, and the least sensitive for 90 Sr

  15. Decontamination efficiency of detergents on the market for the skin contaminated with radioactive materials. The comparative test (1)

    International Nuclear Information System (INIS)

    Miyabe, Kenjiro; Ninomiya, Kazushi; Takasaki, Koji; Horiuchi, Nobuharu; Yasunaka, Hideo; Izumi, Yuichi

    1999-04-01

    Contamination incidence on human body and skin happens sometimes during radiation works in controlled area. The radioactive surface contamination should be removed from the skin as soon as possible for radiation control and exposure management. Titanium oxide paste, which is reserved as a detergent for decontamination, has a satisfactory and reliable result for decontamination effects. The titanium oxide paste, however, has a short preservation period, and must be updated and supplied every serenal months. Decontamination tests for about 60 kinds of detergents on the market were carried out with swine and radioactive material, Ce-144. Radioactive solution of Ce-144 was dropped on the test samples of swine skin, which were left for 5 min or 40 min as it is. Radioactivities of the samples were measured before and after washing by the detergents. As a result of the decontamination tests, 22 kinds of detergents on the market which have a similar decontamination efficiency to the titanium oxide paste were selected. It was also ascertained that the decontamination efficiency of all the detergents decreased on the test samples which were immersed in the radioactive solution for 40 min and wounded on skin surface. (Suetake, M.)

  16. System for removing contaminated surface layers

    International Nuclear Information System (INIS)

    Yoshikawa, Kozo.

    1987-04-01

    The object of the present invention is to offer a new type of useful decontamination system, with which the contaminated surface layers can be removed effectively by injection of such solid microparticles. Liquid carbon dioxide is passed from a liquid carbon dioxide tank via the carbon dioxide supply line into the system for injecting solid carbon dioxide particles. Part of the liquid carbon dioxide introduced into the system is converted to solid carbon dioxide particles by the temperature drop resulting from adiabatic expansion in the carbon dioxide expansion space of the injection system. The solid carbon dioxide particles reach the injection nozzle, which is connected through the expansion space. The carbon dioxide microparticles are further cooled and accelerated by nitrogen gas injected from the nitrogen gas nozzle at the tip of the nitrogen gas supply line, which is connected to a liquid nitrogen tank. The cooled and accelerated solid carbon dioxide microparticles are injected from the injection nozzle for the solid carbon dioxide and directed against the contaminated surface to be cleaned, and, as a result, the surface contamination is removed

  17. Real and alleged hazard of radioactive contamination of seas caused by activities of Russian nuclear fleets

    International Nuclear Information System (INIS)

    Lavkovsky, S.A.

    1999-01-01

    The current paper addresses the assessment results of the degree of danger caused by radioactive contamination of seas by wastes from activities of nuclear fleets compared to the results obtained in other works, specifically, in the IASAP program

  18. Investigating the contamination of accelerated radioactive beams with an ionization chamber at MINIBALL

    CERN Document Server

    Zidarova, Radostina

    2017-01-01

    My summer student project involved the operation and calibration of an ionization chamber, which was used at MINIBALL for investigating and determining the contamination in post-accelerated radioactive beams used for Coulomb excitation and transfer reaction experiments.

  19. The use of radiochemical analysis for detecting biotracers of food radioactive contamination in Cherkasy Region

    International Nuclear Information System (INIS)

    Matvyijenko, D.G.

    2003-01-01

    Stable biotracers of radioactive contamination according to the findings of analytical control of the foodstuffs was determined. The use of radiochemical analysis for determining the activity of the foodstuffs and water (Sr-90, Cs-137) was evaluated

  20. Decrease of radioactive contamination by official wine-making procedures

    International Nuclear Information System (INIS)

    Foerstel, H.; Steffens, W.

    1993-01-01

    A contamination with strontium may be lowered by precipitation as tartaric acid complex, a contamination with cesium or cobalt by precipitation of hexacyanoferrates, both accepted wine-making techniques. Contaminated must was obtained both by addition of nuclides to products from the wine harvest or better by growing wine plants on contaminated soils. (orig.) [de

  1. Smears for determinations surface unfixed tritium contamination

    International Nuclear Information System (INIS)

    Postolache, Cristian; Matei, Lidia

    2003-01-01

    The present paper describes a method of obtaining expanded polystyrene with hydrophilized surface smears by radioinduced grafting of acrylic acid. The grafting was carried out by using a 60 Co γ radiation source. The variation of grafting rates as a function of dose range and absorbed dose was established. Grafting radiochemical rates were determined by radiometric methods using acrylic acid labeled with tritium as a grafting agent. The sampling coefficients and the reproducibility were analyzed as a function of the nature of the contaminated surface. (authors)

  2. Radioactivity Measurements on Glazed Ceramic Surfaces

    OpenAIRE

    Hobbs, Thomas G.

    2000-01-01

    A variety of commonly available household and industrial ceramic items and some specialty glass materials were assayed by alpha pulse counting and ion chamber voltage measurements for radioactivity concentrations. Identification of radionuclides in some of the items was performed by gamma spectroscopy. The samples included tableware, construction tiles and decorative tiles, figurines, and other products with a clay based composition. The concentrations of radioactivity ranged from near backgr...

  3. Dalgety Bay: Managing the risks from historic radioactive contamination

    Energy Technology Data Exchange (ETDEWEB)

    Dale, P. [Scottish Environment Protection Agency (United Kingdom)

    2014-07-01

    Discrete radioactive items have been detected on a public beach at Dalgety Bay, Fife near Edinburgh, Scotland since 1990. Dalgety Bay is a New town built on the site of a former military airfield which serviced and decommissioned planes between 1917 and 1959. In 2011, monitoring of the affected foreshore reported hundreds of radium sources on the beach with activities up to 76 MBq. Immediate actions included closure of part of the beach, additional signs and an intensification of the monitoring and recovery programme. In order to determine the potential source and magnitude of the problem a programme of investigation was commissioned by both SEPA and the UK's Ministry of Defence MoD. The investigation programme revealed that the coastline at parts of the bay was made largely of ash and clinker the result of burning of wastes at the time the air base was operational. The depth of these deposits is variable but at times can be metres thick and extent several metres inland. This made ground contained radium sources which were being exposed on the foreshore as marine action eroded the coastline. Current monitoring and recovery programmes continue to recover over 100 sources each month from the beach which is around 800 m long in entirety. The potential health consequences of encountering such a source ranged according to the potential exposure scenario. For walkers passing through the area the external doses are practically zero, however if people remove material either inadvertently or deliberately doses from skin contact can be significant. For the skin doses initial estimates of doses have indicated that the dose rates were around 1 Gray per hour per MBq (to 1 cm{sup 2} ) to the 70 micron skin thickness recommended by ICRP[1] (ICRP, 89). For ingestion doses can be in excess of 100 mSv. The major variables defining the committed effective dose are the initial activity and the diverse range in solubility which is from zero to 36%. The potential doses to date give

  4. Measurement in vivo of the cutaneous contamination provoked by a radioactive solution

    International Nuclear Information System (INIS)

    Lefaix, J.L.; Lombardo, J.; Delacroix, D.

    1996-01-01

    The utilization of unsealed radioactive sources may cause cutaneous contamination accidents. The detriment is function of the dose of irradiation absorbed by the basal layer of the epidermis and mainly depends on the energy of the β rays, the molecular nature of contaminant and the time of contact with the skin. Furthermore, the penetration kinetic of a substance through the skin is influenced by different factors. So as to determine the dose of irradiation absorbed by the basal layer of the epidermis, we have realized different studies of cutaneous contamination in vivo in the pig: in a first study wa have compared cutaneous obsorption of a radioisotope ( 99m TC) diluted in physiological serum, in a aprotic solvent (DMSO) known to enhance the cutaneous permeability, and by varying the pH of the solution. In a second part, we have compared the cutaneous absorption after contamination times of 1 and 5 minutes, and in different hydration states of the skin before contamination. Results of the in vivo cutaneous absorption, for contaminating times of 1 and 5 minutes, have shown a loss of 5 % of external counting of the electrons (external counting of the 120 KeV electron of 99m Tc), one hour after the contamination, for all the chemical vectors. The variation of the contamination time and the state of hydration of the skin before contamination showed similar results. From these experimental results, an exponential distribution model of the radioisotope in the skin has allowed to calculate the dose rate equivalent of irradiation absorbed by the basal layer of the ipidermis: during a contamination of 5 minutes on a surface of 9 cm 2 with 99m Tc, this dose rate equivalent was 0.98 mSv h -1 by 37 kBq cm -2 (μCi cm -2 ). By the Monte-Carlo method in the hypothesis where there is no cutaneous absorption, it was 0.94 mSv h -1 by 37 kBq cm-2. A preliminary experience with a β emitter ( 14 C) has confirmed a less of 5% of the counting in the same experimental conditions

  5. Hydrogeological aspects of radioactive waste disposal into surface formations

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1980-01-01

    Safe disposal is discussed of radioactive wastes in geological surface formations and basic criteria are shown of the radiological protection of population from possible effects of radioactive materials diffused in the environment. Main principles are listed governing the selection of suitable localities with respect to possible interactions of the locality and the storage site with the environment. (author)

  6. Management of commercial high-level and transuranium-contaminated radioactive wastes. Environmental statement

    International Nuclear Information System (INIS)

    1974-09-01

    This Draft Environmental Statement is issued to assess the environmental impact of the AEC's program to manage commercial high-level and transuranium-contaminated radioactive wastes. These are the types of commercial radioactive wastes for which AEC custody is required by present or anticipated regulations. The program consists of three basic parts: development of a Retrievable Surface Storage Facility (RSSF) for commercial high-level waste, using existing technology; evaluating geological formations and sites for the development of a Geological Disposal Pilot Plant (GDPP) which would lead to permanent disposal; and providing retrievable storage for the transuranium-contaminated waste pending availability of permanent disposal. Consideration has been given to all environmental aspects of the program, using waste generation projections through the year 2000. Radiological and other impacts of implementing the program are expected to be minimal, but will be discussed in further environmental statements which will support budget actions for specific repositories. The alternatives discussed in this Draft Environmental Statement are presented. (U.S.)

  7. Optimization of fodder rations for intensive development of cattle-breeding in an radioactive contaminated zone

    International Nuclear Information System (INIS)

    Stolyarov, G.V.

    1999-01-01

    It has been calculated some variants of the optimal structure of milk cow herd's fodder rations in a radioactive contaminated zone in dependence of the contamination density. Rations were balanced in primary nutritive including digestible protein. It has been determined their costs and specific radioactivity of cesium-137. These fodder rations can be recommended to the farms of the Gomel Region suffered from the Chernobyl nuclear power station explosion

  8. Biological cycles of radioactive contaminants; Les cycles biologiques des pollutions radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Michon, M. -G. [Commissariat a l' energie atomique et aux energies alternatives - CEA (France)

    1959-07-01

    Artificial radio-elements (synthesized for scientific or industrial purposes)having been released, may be absorbed by plants or animals, and may eventually involve a catenation of organisms as some feed on the others. All organisms living in a polluted river become more radioactive than the water, which was to be expected, in as much as organisms are hypertonic in respect to sweet water. Conversely, soil brings into play physico-chemical phenomena (absorption) such that plants can get only a small portion of contaminating radio-elements, land animal feeding on such plants are relatively less exposed to contamination, and carnivorous animals feeding on herbivorous are still less exposed. Man, notably is fairly well protected, whereas lower organisms, notably unicellular organisms may suffer (mutations..). Reprint of a paper published in 'Revue de Pathologie Generale et de Physiologie Clinique', n. 707, April 1959, p. 505-514 [French] L'utilisation a des fins pacifiques ou scientifiques conduit au rejet dans le milieu ambiant de radio-elements artificiels. Ces radio-elements seront plus ou moins absorbes par les plantes et les animaux. Cette pollution va gagner tous les etres vivants a travers les chaines alimentaires. Cependant, l'importance relative de ces absorptions varie avec chaque cas particulier. Par exemple, lors du rejet du radio-element dans un fleuve ou un etang, on constate que tous les etres vivants dans ce milieu presentent une radioactivite specifique superieure a celle du milieu. Ceci n'est pas a priori etonnant puisque tous les etres vivant en eaux douces sont hypertoniques vis-a-vis du milieu. Les facteurs de concentration varient avec la nourriture et des exemples precis sont fournis. A l'inverse, lorsqu'il s'agit de la contamination d'un sol, par suite de phenomenes physicochimiques d'absorption, les plantes ne prelevent qu'une faible partie des radio-elements presents. La nourriture etant moins fortement contaminee, les animaux terrestres le

  9. Concrete decontamination: two innovative processes in response to surface or deep contamination

    International Nuclear Information System (INIS)

    CUER, F.; Nadai, A. de; Faure, S.

    2008-01-01

    To meet the future needs in the nuclear industry as regards dismantling and decommissioning, the LPAD (Laboratoire des Procedes Avances de Decontamination) develops new specific techniques to decontaminate concretes: the drying gel process adapted to surface contamination and the electrokinetics process to treat deep contamination. Indeed, because the concrete constitute a porous medium, two types of contamination can be met according to the environment to which is subjected the material. In the case of an accidental or dry contamination, radio elements do not penetrate beyond the first millimeters of the material. The contamination is then considered as surface. On the contrary, the contamination is considered as 'deep' when radioactive ions have diffused deeply under the effects of the natural diffusion. This is the case in fuel storage pond or other many nuclear infrastructures. (authors)

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  11. Evaluating factors affecting the permeability of emulsions used to stabilize radioactive contamination from a radiological dispersal device.

    Science.gov (United States)

    Fox, Garey A; Medina, Victor F

    2005-05-15

    Present strategies for alleviating radioactive contamination from a radiological dispersal device (RDD) or dirty bomb involve either demolishing and removing radioactive surfaces or abandoning portions of the area near the release point. In both cases, it is imperative to eliminate or reduce migration of the radioisotopes until the cleanup is complete or until the radiation has decayed back to acceptable levels. This research investigated an alternative strategy of using emulsions to stabilize radioactive particulate contamination. Emergency response personnel would coat surfaces with emulsions consisting of asphalt or tall oil pitch to prevent migration of contamination. The site can then be evaluated and cleaned up as needed. In order for this approach to be effective, the treatment must eliminate migration of the radioactive agents in the terror device. Water application is an environmental condition that could promote migration into the external environment. This research investigated the potential for water, and correspondingly contaminant, migration through two emulsions consisting of Topein, a resinous byproduct during paper manufacture. Topein C is an asphaltic-based emulsion and Topein S is a tall oil pitch, nonionic emulsion. Experiments included water adsorption/ mobilization studies, filtration tests, and image analysis of photomicrographs from an environmental scanning electron microscope (ESEM) and a stereomicroscope. Both emulsions were effective at reducing water migration. Conductivity estimates were on the order of 10(-80) cm s(-1) for Topein C and 10(-7) cm s(-1) for Topein S. Water mobility depended on emulsion flocculation and coalescence time. Photomicrographs indicate that Topein S consisted of greater and more interconnected porosity. Dilute foams of isolated spherical gas cells formed when emulsions were applied to basic surfaces. Gas cells rose to the surface and ruptured, leaving void spaces that penetrated throughout the emulsion. These

  12. Radioactive contamination in the environs of the Hanford Works for the period October, November, December 1949

    Energy Technology Data Exchange (ETDEWEB)

    Paas, H.J.; Singlevich, W.

    1950-03-02

    This report summarizes the measurements made for radioactive contamination in the environs of the Hanford Works. The principal sources of the radioactivity originating as a result of operations at Hanford which affect the environment in this area are the two waste stacks in the separations area and the cooling water from the four pile areas. Measurements are also made on samples taken from the Hanford waste systems which are primarily confined within the project proper. Although monthly summaries of these data are reported in Health Instrument Divisions Environs reports, a somewhat more detailed discussion of these data is covered in the quarterly report. In this manner, a better evaluation of possible trends can be detected as a result of the increased number of measurements made available by combining the data for a three month period. The following areas are discussed: meteorology, radioactive contamination of vegetation, airborne contamination and air radiation levels, radioactive contamination in Hanford wastes, radioactive contamination in the Columbia and Yakima rivers; beta activity in rain and snow, and radioactive contamination in drinking water and test wells.

  13. Precaution against radioactive contamination of steel products in Germany

    International Nuclear Information System (INIS)

    Ewers, E.; Schulz-Klemp, V.; Steffen, R.

    1999-01-01

    Regulations for handling of radioactive materials in Germany. Engagement of the Germany Iron and Steel Institute (VDEh) since the end of the eighties and measures taken. Level of radioactivity in uncontaminated steel products. Agreements between steel industry and scrap supplying industry as well as terms of delivery. Actual status of equipment for detection of radioactivity in the German steel plants. Demands of steel users for clean steel. (author)

  14. Radioactive Waste Management and Environmental Contamination Issues at the Chernobyl Site

    International Nuclear Information System (INIS)

    Napier, Bruce A.; Schmieman, Eric A.; Voitsekhovitch, Oleg V.

    2007-01-01

    The destruction of the Unit 4 reactor at the Chernobyl Nuclear Power Plant resulted in the generation of radioactive contamination and radioactive waste at the site and in the surrounding area (referred to as the Exclusion Zone). In the course of remediation activities, large volumes of radioactive waste were generated and placed in temporary near surface waste-storage and disposal facilities. Trench and landfill type facilities were created from 1986 to 1987 in the Chernobyl Exclusion Zone at distances 0.5 to 15 km from the NPP site. This large number of facilities was established without proper design documentation, engineered barriers, or hydrogeological investigations and they do not meet contemporary waste-safety requirements. Immediately following the accident, a Shelter was constructed over the destroyed reactor; in addition to uncertainties in stability at the time of its construction, structural elements of the Shelter have degraded as a result of corrosion. The main potential hazard of the Shelter is a possible collapse of its top structures and release of radioactive dust into the environment. A New Safe Confinement (NSC) with a 100-years service life is planned to be built as a cover over the existing Shelter as a longer-term solution. The construction of the NSC will enable the dismantlement of the current Shelter, removal of highly radioactive, fuel-containing materials from Unit 4, and eventual decommissioning of the damaged reactor. More radioactive waste will be generated during NSC construction, possible Shelter dismantling, removal of fuel containing materials, and decommissioning of Unit 4. The future development of the Exclusion Zone depends on the future strategy for converting Unit 4 into an ecologically safe system, i.e., the development of the NSC, the dismantlement of the current Shelter, removal of fuel containing material, and eventual decommissioning of the accident site. To date, a broadly accepted strategy for radioactive waste

  15. Radioactive waste management and environmental contamination issues at the Chernobyl site.

    Science.gov (United States)

    Napier, B A; Schmieman, E A; Voitsekovitch, O

    2007-11-01

    The destruction of the Unit 4 reactor at the Chernobyl Nuclear Power Plant resulted in the generation of radioactive contamination and radioactive waste at the site and in the surrounding area (referred to as the Exclusion Zone). In the course of remediation activities, large volumes of radioactive waste were generated and placed in temporary near-surface waste storage and disposal facilities. Trench and landfill type facilities were created from 1986-1987 in the Chernobyl Exclusion Zone at distances 0.5-15 km from the nuclear power plant site. This large number of facilities was established without proper design documentation, engineered barriers, or hydrogeological investigations and they do not meet contemporary waste-safety requirements. Immediately following the accident, a Shelter was constructed over the destroyed reactor; in addition to uncertainties in stability at the time of its construction, structural elements of the Shelter have degraded as a result of corrosion. The main potential hazard of the Shelter is a possible collapse of its top structures and release of radioactive dust into the environment. A New Safe Confinement (NSC) with a 100 y service life is planned to be built as a cover over the existing Shelter as a longer-term solution. The construction of the NSC will enable the dismantlement of the current Shelter, removal of highly radioactive, fuel-containing materials from Unit 4, and eventual decommissioning of the damaged reactor. More radioactive waste will be generated during NSC construction, possible Shelter dismantling, removal of fuel-containing materials, and decommissioning of Unit 4. The future development of the Exclusion Zone depends on the future strategy for converting Unit 4 into an ecologically safe system, i.e., the development of the NSC, the dismantlement of the current Shelter, removal of fuel-containing material, and eventual decommissioning of the accident site. To date, a broadly accepted strategy for radioactive waste

  16. 10 CFR Appendix D to Part 835 - Surface Contamination Values

    Science.gov (United States)

    2010-01-01

    ... posting of contamination and high contamination areas in accordance with § 835.603(e) and (f) and...-228, Th-230, Th-228, Pa-231, Ac-227, I-125, I-129 20 500 Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232... pressure, and then assessing the amount of radioactive material on the swipe with an appropriate instrument...

  17. Airborne iodine-125 arising from surface contamination

    International Nuclear Information System (INIS)

    Kwok, C.S.; Hilditch, T.E.

    1982-01-01

    Measurements of airborne 125 I were made during the subdivision of 740 MBq stocks of 125 I iodide solution in a hospital dispensary. Within the fume cupboard the mean airborne 125 I concentration was 3.5 +- 2.9 kBqm -3 . No airborne concentration contamination was found outside the fume cupboard during these dispensing sessions. The airborne 125 I concentration arising from deliberate surface contamination (50 μl, 3.7-6.3 MBq) of the top of a lead pot was measured at a height simulating face level at an open work bench. There was a progressive fall in airborne concentration over seven days but even then the level was still significantly above background. Measurements made with the extraction system of the fume cupboard in operation were 2-3 times lower. (U.K.)

  18. Methodological guide: management of industrial sites potentially contaminated by radioactive substances; Guide methodologique: gestion des sites industriels potentiellement contamines par des substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    At the request of the Ministries of Health and the Environment, IPSN is preparing and publishing the first version of the methodological guide devoted to managing industrial sites potentially contaminated by radioactive substances. This guide describes a procedure for defining and choosing strategies for rehabilitating such industrial sites. (author)

  19. Effects of processing techniques on the radioactive contamination of food

    International Nuclear Information System (INIS)

    Bovard, P.; Delmas, J.; Grauby, A.

    Following contamination of cultures of rice, grapes and various vegetables by 90 Sr and 137 Cs, the effect of processing and cooking techniques on the contamination of the food-stuff was investigated [fr

  20. The Norwegian Radiation Protection Authority leads international cooperation on radioactive contamination in the Arctic

    International Nuclear Information System (INIS)

    1995-01-01

    In cooperation with Russia, Norway is responsible for the part of Arctic Monitoring and Assessment Programme (AMAP) concerning radioactivity. An assessment of the consequences of radioactive contamination for the environment in northern areas will be an important part of AMAP's report to the Ministers of the Environment in the eight participating countries in 1996. The report will contain an overview of the sources of the contamination and the level of radioactivity in the environment, in addition to an evaluation of the consequences for humans and the environment

  1. Imaging plant leaves to determine changes in radioactive contamination status in Fukushima, Japan.

    Science.gov (United States)

    Nakajima, Hiroo; Fujiwara, Mamoru; Tanihata, Isao; Saito, Tadashi; Matsuda, Norihiro; Todo, Takeshi

    2014-05-01

    The chemical composition of plant leaves often reflects environmental contamination. The authors analyzed images of plant leaves to investigate the regional radioactivity ecology resulting from the 2011 accident at the Fukushima No. 1 nuclear power plant, Japan. The present study is not an evaluation of the macro radiation dose per weight, which has been performed previously, but rather an image analysis of the radioactive dose per leaf, allowing the capture of various gradual changes in radioactive contamination as a function of elapsed time. In addition, the leaf analysis method has potential applications in the decontamination of food plants or other materials.

  2. Outcomes of experimental researches on stainless steel decontamination from radioactive contamination using electric slag remelting method

    International Nuclear Information System (INIS)

    Vurim, A.D.; Pakhnitz, A.V.; Trukhachev, A.G.; Bukhtoyarov, O.I.; Goncharov, A.Ye.

    2003-01-01

    Full text: Institute of Atomic Energy prepared and conducted the experiments the purpose of researching a possibility of applying of stainless steel electric slag remelting for its decontamination from radioactive contamination. The activities were conducted at participating of the specialists of Kurgan State University, Kurgan (Russian Federation). A stand, which includes the electroslag furnace (power - 150 kW, current - to 3000 A) and auxiliary equipment (the system of common and special ventilation, system of remote control, system of parameters measuring and registering and others) was created to conduct the experiments. The properties of slag compositions were researched in the course of experiments preparation. Oxide (CaO-Al 2 O 3 - CaO-SiO 2 - MgO-B 2 O 3 ) and fluoride-oxide (CaF 2 -SiO 2 - MgF 2 -SiO 2 ) slag systems and some their modifications were chosen to research physical and chemical properties. Physical and chemical properties of the slag systems were experimentally researched and it included: measuring of surface tension using the method of maximum pressure in a gas bubble (at the same time density was measured); measuring of slag alloys electrical conductivity; measuring of melt volt-ampere characteristics. The flue tubes of high temperature reactor gas cooling KET technological channels were chosen as a source of radioactive contaminated stainless steel. This reactor is meant for testing of the fuel pin and FA of the nuclear pulse propulsion. Decontamination effect for all the remelted flue tubes was indirectly confirmed by the outcomes of measuring of radioactive radiation dose rate of the materials, extracted of the crystallizer after experiments finishing. The outcomes of the experiments show that the following processes pass at electroslag remelting of radioactively contaminated steel: uranium extraction from steel; uranium transfer from steel to slag; saving or insignificant modification of steel initial composition; radionuclides deposing

  3. Development of apparatus for surveying uranium surface contamination quantity

    International Nuclear Information System (INIS)

    Wang Qingheng; Han Jingquan

    1994-11-01

    An apparatus for measuring uranium contamination of the surface of reactor plate component is described. The searching unit of the apparatus is a large surface multi-wire proportional counter. The cathode of the counter is made of stainless steel with low radioactive background, the window is made of film which is plated with aluminum about 6 μm; and the anode is mad by gild tungsten wire of 0.025 mm diameter. The sensitive area of the counter is 1113 mm x 100 mm. It has been shown that the intrinsic radioactive background of the apparatus is 0.002 cpm/cm 2 (2 count/min). The detecting efficiency is 67% for enriched uranium source (2π solid angle). The stability is 0.84% within 24 hour (including detector, high voltage power supply, amplifier, discriminator, computer, type and display system). The lower detection limit of the apparatus is 4.6 x 10 -10 g/cm 2 (for 20% 235 U, 0.13% 234 U, 79.64% 238 U). The apparatus can present timing by a computer controlling, and it also has the following functions: displaying, automatic alarming, classifying and typing the results. (2 tabs., 7 figs.)

  4. Characterization of naturally occurring radioactive materials and Cobald-60 contaminated ferrous scraps from steel industries

    International Nuclear Information System (INIS)

    Chao, H.E.; Chiu, H.S.; Hunga, J.Y.; His, H.W.; Chen, Y.B.

    2002-01-01

    Since the occurrence of radioactively contaminated rebar incident in 1992, steel industries in Taiwan were encouraged by Atomic Energy Council (AEC) to install portal monitor to detect the abnormal radiation in shipments of metal scrap feed. From 1994 through 1999, there were 53 discoveries of radioactivity in ferrous scraps by steel companies. These include 15 orphan radioactive sources, 16 cobalt-60 contaminated rebars, 20 Naturally Occurring Radioactive Material (NORM) contaminated scraps, and two unknowns. Most NORM-contaminated scraps were from abroad. The NORM and cobalt-60 contaminated scraps were taken from the steel mills and analyzed in laboratory. The analytical results of scales and sludge sampled from NORM-contaminated scraps combining with the circumstantial evidences indicate that five possible industrial processes may be involved. They are oil production and treatment, heavy mineral sand benefication and rare earth processing, copper mining and processing, recovery of ammonium chloride by lime adsorption in Ammonium-soda process, and tailing of uranium enrichment process. The cobalt-60 activity and trace elements concentrations of contaminated rebars confirm that all of them were produced domestically in the period from Oct. 1982 to Jan. 1983, when the cobalt-60 sources were lost and entered the electric arc furnace to produce the contaminated rebars. (author)

  5. Evaluation of Radioactive Contamination in Hamadan Nuclear Medicine Centers Using Wipe Technique

    Directory of Open Access Journals (Sweden)

    N. Rostampour

    2014-02-01

    .Conclusion: In centers 1 and 2, most of the radioactive contamination occurred under the hood due to labeling of radiopharmaceuticals activity. Also, in center 3, the highest contamination rate belonged to patients’ corridor that could be due to frequent the area. According to this subject, necessary measures in this regard should be considered by the department responsible for health physics.

  6. A Study on the Method to Discriminate Between the Internal and External Radioactive Contamination Using Whole Body Counter

    International Nuclear Information System (INIS)

    Kong, T. Y.; Kim, H. G.; Yang, H. Y.; Kang, D. W.; Lim, S. N.; Kim, H. J.; Jin, H. H.; Lee, S. G.; Park, S. C.

    2006-01-01

    Whole Body Counter (WBC) is used to identify and measure the radioactivity in the body of human beings in a nuclear power plants (NPPs). In domestic NPPs, it is prescribed that all workers should take a whole body counting after radiation works if the possibilities of radioactive contamination exist or the radioactivity is detected by a portal monitoring. It is, however, found that the external skin contamination is occasionally estimated as the internal radioactive contamination. In this case, the worker assumed to be detected is recommended to take showers for the decontamination of skin and take a whole body counting again. Although the detected radioactivity is reduced remarkably after several decontaminations, confirmed as the external skin contamination, it is determined finally as an internal exposure if the radioactivity is still detected in the body of worker. The amount of detected radioactivity can be much higher than that of the expected for this mistaken contamination since the radioisotopes attached to skin come to be close to the detectors of WBC. Finally, this makes the misjudgment of the external skin contamination as well as the excessively conservative estimation of radioactive contamination. In this study, several experiments were carried out to discriminate between the internal and external radioactive contamination using the humanoid phantom and WBC. Preliminary experimental results indicated that the use of front and backside counts could be applied to the discrimination of the external skin contamination and the difference of detected radioactivities between front and backside counts was less than about factor 2 for the internal contamination

  7. Radioactivity Measurements on Glazed Ceramic Surfaces.

    Science.gov (United States)

    Hobbs, T G

    2000-01-01

    A variety of commonly available household and industrial ceramic items and some specialty glass materials were assayed by alpha pulse counting and ion chamber voltage measurements for radioactivity concentrations. Identification of radionuclides in some of the items was performed by gamma spectroscopy. The samples included tableware, construction tiles and decorative tiles, figurines, and other products with a clay based composition. The concentrations of radioactivity ranged from near background to about four orders of magnitude higher. Almost every nuclide identification test demonstrated some radioactivity content from one or more of the naturally occurring radionuclide series of thorium or uranium. The glazes seemed to contribute most of the activity, although a sample of unglazed pottery greenware showed some activity. Samples of glazing paints and samples of deliberately doped glass from the World War II era were included in the test, as was a section of foam filled poster board. A glass disc with known (232)Th radioactivity concentration was cast for use as a calibration source. The results from the two assay methods are compared, and a projection of sensitivity from larger electret ion chamber devices is presented.

  8. Radioactive contamination of Danish territory after core-melt accidents at the Barsebaeck power plant

    International Nuclear Information System (INIS)

    Gjoerup, H.L.; Jensen, N.O.; Hedemann Jensen, P.; Kristensen, L.; Nielsen, O.J.; Petersen, E.L.; Petersen, T.; Roed, J.; Thykier-Nielsen, S.; Heikel Vinter, F.; Warming, L.; Aarkrog, A.

    1982-03-01

    An assessment is made of the radioactive contamination of Danish territory in the event of a core-melt accident at the Barsebaeck nuclear power plant in Sweden. Accidents including both core melt-down and containment failure are considered. Consequences are calculated for a BWR-3 release under common meteorological conditions and for a BWR-2 release under extreme meteorological conditions. Calculations are based on experiments and theoretical work relating to deposition velocities for different types of surface, shielding effect of structures, and weathering. The effects are described of different dose-reducing measures, e.g., decontamination, relocation, destruction of contaminated foodstuffs. The collective effective dose equivalent from external gamma radiation from deposited activity integrated over a time period of 30 years, is calculated to be 3.6 Megamanrem in the BWR-3 case without dose-reducing measures. For the BWR-2 case, the corresponding dose is approx. 41 Megamanrem. A combination of temporary relocation, hosing of roads etc. and digging of gardens is estimated to reduce these doses to approx. 2.5 Megamanrem and approx. 15 Megamanrem, respectively. The collective committed effective dose equivalent from the consumption of contaminated foodstuffs is calculated to 23 Megamanrem in the BWR-3 case without dose-reducing measures. This dose could be reduced to 0.2 Megamanrem if contaminated crops are destroyed during the first year after the accident and if changes are made in agricultural production in the contaminated area. The corresponding doses in the BWR-2 case would be 197 Megamanrem and 1.4 Megmanrem, respectively. (author)

  9. Radioactive contamination status of an elementary school in southern Miyagi Prefecture, Japan, four years after decontamination

    International Nuclear Information System (INIS)

    Yamaguchi, Toshiro; Sato, Mitsuyoshi; Nagakubo, Kazuyoshi

    2017-01-01

    We investigated the radioactive contamination status of an elementary school in southern Miyagi Prefecture, Japan, four years after decontamination. The radioactive dose rate was measured in the playground (n = 36), back yard (n = 1), parking lot (n = 3), and gutters (n = 30) with a thallium-activated sodium iodide scintillation detector. In addition, topsoil from the playground and gutters sediment were measured with a high-purity germanium semiconductor detector, and sand from the parking lot and sediment from gutters was imaged following an autoradiography method. The mean radioactive dose rate in the playground was almost 0.08 μSv/h. The dose rate was higher at sites facing the mountains, near the main gate, and by the front entrance of the school building. Meanwhile, the radioactive cesium (Cs) concentration of sediment imaged using autoradiography was > 8,000 Bq/kg. These results indicated that the radioactive dose rates in the decontaminated school were below the threshold for being a health hazard. However, the topsoil in the playground had been re-contaminated with radioactive Cs, which had likely been transported via dirt attached to children's shoes and car tires. In addition, the radioactive sediment in the gutters had likely been contaminated by rainwater, suggesting that radioactive protection is necessary when handling gutter sediment. (author)

  10. Radioactive contamination of the Dnepr-Sozh river basin in Belarus after the accident at the Chernobyl NPP

    International Nuclear Information System (INIS)

    Zhukova, O.M.; Matveenko, I.I.; Pokumejko, Yu.M.; Shagalova, E.D.

    1998-01-01

    Systematic control over the radioactive contamination of surface waters is carried out at five main rivers of Belarus: Dnepr, Sozh, Pripyat, Iput, Besed. The experimental watershed of Iput river (Dnepr-Sozh basin) have been chosen for revealing the general rules of radioactive contamination of the rivers of Belarus on the basis of generalization of the monitoring data and field investigations. It has been found that transport of radionuclides on suspended solids is one of the main forms of migration of radionuclides in the river (caesium-137 in particular). Thus, the analysis of contamination of the rivers of Belarus has shown that the most intensive runoff of radionuclides from the territories of the watershed occurs in the head of the Dnepr basin, namely by its tributaries, Iput and Sozh. The annual runoff of radionuclides in soluble form by the rivers of Belarus in 1987-1996 has decreased significantly. Transport of radioisotopes with suspended and drawn wash loads significantly affects their migration and its contribution to the total runoff of radionuclides has increased with time. The runoff of radionuclides with transported wash loads varied within 20-80% from the total runoff of radionuclides. Sedimentation of river suspended load carrying radionuclides in the sites with slow river flow creates local movable ecologically dangerous centres of accumulation of radionuclides in bottom sediments particularly in front of the diverting dams. Existence of such centres of radioactive contamination requires their monitoring, assessment of their possible effects, and, if necessary, their decontamination

  11. Assessment of the environmental radioactive contamination levels by depleted uranium after NATO aggression on FR Yugoslavia

    International Nuclear Information System (INIS)

    Pavlovic, S.; Pavlovic, R.; Markovic, S; Plecas, I.

    2001-01-01

    During NATO aggression on FR Yugoslavia various ammunition have been used, some of them for the first time. Among others, 30 mm bullets with depleted uranium (DU) penetrators have been used. Radioactivity contamination surveys have started during the war due to indications that DU is used in cruise missiles. Besides that, there were a lot of radioactivity analysis of food, drinking water etc. Some of the obtained results are presented in this paper. Depleted uranium ammunition can permanently contaminate environment and so produce effects on population. Relation of the international radiation and environmental protection standards and contamination levels are discussed as well. (author)

  12. DOE`s radioactively - contaminated metal recycling: The policy and its implementation

    Energy Technology Data Exchange (ETDEWEB)

    Warren, S.; Rizkalla, E.

    1997-02-01

    In 1994, the Department of Energy`s Office of Environmental Restoration initiated development of a recycling policy to minimize the amount of radioactively-contaminated metal being disposed of as waste. During the following two years, stakeholders (including DOE and contractor personnel, regulators, members of the public, and representatives of labor and industry) were invited to identify key issues of concern, and to provide input on the final policy. As a result of this process, a demonstration policy for recycling radioactively-contaminated carbon steel resulting from decommissioning activities within the Environmental Management program was signed on September 20, 1996. It specifically recognizes that the Office of Environmental Management has a tremendous opportunity to minimize the disposal of metals as waste by the use of disposal containers fabricated from contaminated steel. The policy further recognizes the program`s demand for disposal containers, and it`s role as the major generator of radioactively-contaminated steel.

  13. Air monitoring data reveal previously unknown contamination at radioactive waste disposal area, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Kraig, D.H.; Conrad, R.C.

    2000-01-01

    Air monitoring at Area G, the low-level radioactive waste disposal area at Los Alamos National Laboratory, revealed increased air concentrations of 239 Pu and 241 Am at one location along the north boundary. This air monitoring location is a couple of meters north of a dirt road used to access the easternmost part of Area G. Air concentrations of 238 Pu were essentially unaffected which was puzzling because both 238 Pu and 239 Pu are present in the local, slightly contaminated soils. Air concentrations of these radionuclides increased about a factor of ten in early 1995 and remained at those levels until the first quarter of 1996. During the spring of 1996 air concentrations again increased by a factor of about ten. No other radionuclides were elevated, and no other Area G stations showed elevations of these radionuclides. After several formal meetings did not provide an adequate explanation for the elevations, a gamma-survey was performed and showed a small area of significant contamination just south of the monitor location. We found that in February 1995, a trench for a water line had been dug within a meter or so of the air stations. Then, during early 1996, the dirt road was rerouted such that its new path was directly over the unknown contamination. It appears that the trenching brought contaminated material to the surface and caused the firs rise in air concentrations and then the rerouting of the road over the contamination caused the second rise, during 1996. We also found that during 1976 and 1977 contaminated soils from the clean-up of an old processing facility had been spread over the filled pits in the vicinity of the air monitors. These soils, which were probably the source of the air contamination, were very low in 238 Pu which explains why we saw very little 238 Pu in the increased air concentrations. A layer of gravel and sand was spread over the contaminated area. Although air concentrations of 239 Pu and 241 Am dropped considerably, they have

  14. Cleanup procedures at the Nevada Test Site and at other radioactively contaminated sites including representative costs of cleanup and treatment of contaminated areas

    International Nuclear Information System (INIS)

    Talmage, S.S.; Chilton, B.D.

    1987-09-01

    This review summarizes available information on cleanup procedures at the Nevada Test Site and at other radioactively contaminated sites. Radionuclide distribution and inventory, size of the contaminated areas, equipment, and cleanup procedures and results are included. Information about the cost of cleanup and treatment for contaminated land is presented. Selected measures that could be useful in estimating the costs of cleaning up radioactively contaminated areas are described. 76 refs., 16 tabs

  15. Radioactive contamination in the marine environment adjacent to the outfall of the radioactive waste treatment plant at ATOMFLOT, northern Russia.

    Science.gov (United States)

    Brown, J E; Nikitin, A; Valetova, N K; Chumichev, V B; Katrich, I Yu; Berezhnoy, V I; Pegoev, N N; Kabanov, A I; Pichugin, S N; Vopiyashin, Yu Ya; Lind, B; Grøttheim, S; Sickel, M; Strand, P

    2002-01-01

    RTP "ATOMFLOT" is a civilian nuclear icebreaker base located on the Kola Bay of northwest Russia. The objectives of this study were to determine the distributions of man-made radionuclides in the marine environment adjacent to the base, to explain the form of the distributions in sediments and to derive information concerning the fate of radionuclides discharged from ATOMFLOT. Mean activity concentrations (d.w.) for surface sediment, of 63 Bq kg(-1 137Cs, 5.8 Bq kg(-1) 90Sr and 0.45 Bq kg(-1 239,240)Pu were measured. Filtered seawater activity levels were in the range of 3--6.9 Bq m(-3) 137Cs, 2.0-11.2 Bq m(-3) 90Sr, and 16-40 m Bq m(-3), 239,240Pu. Short-lived radionuclides were present at sediment depths in excess of 10cm indicating a high degree of sediment mixing. Correlations of radionuclide activity concentrations with grain-size appear to be absent; instead, the presence of relatively contaminated sediment appears to be related to the existence of radioactive particles.

  16. Atmospheric-Pressure Plasma Cleaning of Contaminated Surfaces

    International Nuclear Information System (INIS)

    Hicks, Robert F.; Herrmann, Hans W.

    2003-01-01

    The objective of this work is to demonstrate a practical, atmospheric pressure plasma tool for the surface decontamination of radioactive waste. Decontamination of radioactive materials that have accumulated on the surfaces of equipment and structures is a challenging and costly undertaking for the US Department of Energy. Our technology shows great potential for accelerating this clean up effort

  17. Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K

    2001-04-01

    The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology.

  18. Development of an automatic smear sampler and evaluation of surface contamination

    International Nuclear Information System (INIS)

    Seo, B. K.; Lee, B. J.; Lee, K. W.; Park, J. H.

    2004-01-01

    The surface contamination level of a radiation-controlled area is measured periodically according to atomic energy law and connection regulations. The measurement of surface contamination by an indirect method is subject to various kinds of error depending on the sampling person and consumes much time and effort in the sampling of large nuclear facilities. In this research, an automatic smear sampler is developed to solve these problems. The developed equipment is composed of a rotating sampling part, a sample transferring part, a power supply part a control part, and vacuum part. It improved the efficiency of estimation of the surface contamination level achieved periodically in a radiation-controlled area. Using an automatic smear sampler developed in this research, it is confirmed that radioactive contaminated materials are uniformly transferred to smear paper more than any sampling method by an operator. (authors)

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

    International Nuclear Information System (INIS)

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

    2008-05-01

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

  20. Packaging, Transportation, and Disposal Logistics for Large Radioactively Contaminated Reactor Decommissioning Components

    International Nuclear Information System (INIS)

    Lewis, Mark S.

    2008-01-01

    and disposal regulations and criteria or if special authorizations must be granted to transport and/or dispose. The U.S. DOT routinely issues special permits for large components where compliance with regulatory or acceptance criteria is impractical or impossible to meet. Transportation and disposal safety must be maintained even under special permits or authorizations. For example, if transported un-packaged, performance analysis must still be performed to assess the ability of the large component's outer steel shell to contain the internal radioactive contamination under normal transportation conditions and possibly incidence normal to transportation. The dimensions and weight of a large component must be considered when determining the possible modes of transportation (rail, water, or highway). At some locations, rail and/or barge access is unavailable. Many locations that once had an active rail spur to deliver new construction materials and components have let the spur deteriorate to the point that repair and upgrade of the spur is no longer economically feasible. Barge slips that have not been used since new plant construction require significant repair and/or dredging. Short on-site haul routes must be assessed for surface and subsurface conditions, as well as longer off-site routes. Off-site routes require clearance approvals from the regulatory authorities or, in the case of rail transport, the rail lines. Significant engineering planning and analysis must be performed during the pre-mobilization. In conclusion, the packaging, transportation, and disposal of large, oversized radioactively contaminated components removed during plant decommissioning is complex. However, over the last 15 years, a 100 or more components have been safely and compliantly packaged and transported for processing and/or disposal

  1. Development of the Discrimination Programs between the Internal and External Radioactive Contamination of Workers Using a Whole Body Counter

    International Nuclear Information System (INIS)

    Kong, T. Y.; Kim, H. G.; Lim, S. N.; Kim, H. J.; Jin, H. H.; Lee, S. G.; Park, S. C.

    2006-01-01

    A whole body counter (WBC) is used to identify and measure the radioactivity in the body of human beings in a nuclear power plant (NPP). In domestic NPPs, several whole body counters are in operation to monitor the internal radioactive contamination of workers. All workers take a whole body counting after radiation works if there is high possibility of radioactive contamination or the radioactivity is detected by portal monitoring. It is, however, found that the external contamination is occasionally estimated as the internal radioactive contamination. In this case, the worker is recommended to take showers for the decontamination of skin and take a whole body counting again. Although the detected radioactivity is reduced remarkably after several decontaminations, confirmed as the external contamination, it is determined finally as an internal contamination if the radioactivity is still detected in the body of worker. The amount of detected radioactivity can be much higher than that of the expected for this mistaken contamination since the radioisotopes attached to skin come to be close to the detectors of WBC. Finally, this makes not only the misjudgment of the external contamination as the internal contamination, but also the excessively conservative estimation of radioactive contamination. In this study, several experiments were carried out to set up the discrimination program between the internal and external radioactive contamination using the humanoid phantom and a whole body counter. After the analysis of experimental results, we found that the use of front and backside counts could be applied to the discrimination of the external contamination and the ratio of detected radioactivities between front and backside counts was more than about factor 2 for the external contamination

  2. Radiobiological significance of radioactive contamination - summary assessment based on great number of measurements

    Energy Technology Data Exchange (ETDEWEB)

    Angelov, V [Civil Defence Administration, Sofia (Bulgaria); Bonchev, Ts; Mavrodiev, V; Kyrdzhilov, N [Sofia Univ. (Bulgaria). Fizicheski Fakultet

    1996-12-31

    In order to facilitate quantitative and qualitative characterisation of radioactive contamination the authors introduce a relative estimate of radionuclide activity by setting as a reference the most abundant element -Co-60 in the case of the Kozloduy NPP. The ratio {eta}{sub i} of the mean annual permissible concentration in air for each radionuclide (RPC-92) to that of Co-60 is calculated. It is found that {eta}{sub i} has the same or close values for groups of radionuclides, e.g. {eta}{sub i} = 2.10{sup -4} for {sup 238} Pu, {sup 239} Pu, {sup 240} Pu, {sup 241} Am, {sup 244} Cm; {eta}{sub i} = 5 for {sup 89} Sr, {sup 91} Y; {sup 93} Nb, {sup 134} Cs, {sup 137} Cs; {eta}{sub i} = 50 for {sup 55} Fe, {sup 63} Ni, {sup 95} Zr, {sup 95} Nb, {sup 140} Ba, {sup 140} La. Then it is compared to the experimentally measured values of the same quantity {eta}{sub iexp}, derived from surface contamination data. The ratio {eta}{sub iexp}/{eta}{sub i} is plotted against log {eta}{sub i}. The resulting nomograms give graphic representation of the radiobiological significance of various radionuclide groups. Data from different locations at the Kozloduy NPP are presented. It is found that the alpha emitter contamination has highest values in the Unit 1 (WWER-440) control rooms after repair. The Unit 5 (WWER-1000) has lower alpha contamination compared to WWER-440 units. 1 ref., 5 figs., 1 tab.

  3. Present situation of radioactive contamination in and around the former Soviet Union's Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Yamamoto, M.; Hoshi, M.; Takada, J.; Tsukatani, T.; Oikawa, S.; Yoshikawa, I.; Takatsuji, T.; Sekerbaev, A. Kh.; Gusev, B.I.

    2001-01-01

    Field missions were sent to the Semipalatinsk regions to investigate the present radioecological situation as a result of the radioactive fallout from nuclear test explosions carried out at the former Soviet Union's Semipalatinsk nuclear test site (SNTS). For this purpose, surface and core soil samples were collected at more than 60 sites, including several settlements such as Dolon, Chagan and Sarzhal, within and outside the SNTS territory. The radioactivities of long-lived radionuclides, 137 Cs, 238 Pu and 239,240 Pu, and the atomic ratio of 240 Pu/ 239 Pu were determined in combination with non-destructive g-ray spectrometric method and radiochemical separation followed by a-particle spectrometric and/or ICP-MS methods. The results showed a distinction of 137 Cs and 239,240 Pu inventories in soil depending on a sampling sites. Although 137 Cs was within typical environmental levels except for the area near the first nuclear test site and Balapan, 239,240 Pu was at elevated levels in all areas we visited. This high Pu contamination was recognized to be due to the weapons-grade Pu from the SNTS by the measurement of 240 Pu/ 239P u atomic ratio in soil samples. (author)

  4. Application of a modified electrochemical system for surface decontamination of radioactive metal waste

    International Nuclear Information System (INIS)

    Lee, J.H.; Lim, Y.K.; Yang, H.Y.; Shin, S.W.; Song, M.J.

    2003-01-01

    Conventional and modified electrolytic decontamination experiments were performed in a solution of sodium sulfate for the decontamination of carbon steel as the simulated metal wastes which are generated in large amounts from nuclear power plants. The effect of reaction time, current density and concentration of electrolytes in the modified electrolytic decontamination system were examined to remove the surface contamination of the simulated radioactive metal wastes. As for the results of this research, the modified electrochemical decontamination process can decontaminate more effectively than the conventional decontamination process by applying different anode material which causes higher induced electro-motive forces. When 0.5 M sodium sulfate, 0.4 A/cm 2 current density and 30 minutes reaction time were applied in the modified process, a 16 μm thickness change that is expected to remove most surface contamination in radioactive metal wastes was achieved on carbon steel which is the main material of radioactive metal waste in nuclear power plants. The decontamination efficiency of metal waste showed similar results with the small and large lab-scale modified electrochemical system. The application of this modified electrolytic decontamination system is expected to play a considerable role for decontamination of radioactive metal waste in nuclear power plants in the near future. (author)

  5. Complex relationship between groundwater velocity and concentration of radioactive contaminants

    International Nuclear Information System (INIS)

    Kaszeta, F.E.; Bond, F.W.

    1980-01-01

    This paper uses the results from the Multi-component Mass Transport model to examine the complex interrelationship between groundwater velocity and contaminant dispersion, decay, and retardation with regard to their influence on the contaminant concentration distribution as it travels through the geosphere to the biosphere. The rate of transport of contaminants through the geosphere is governed by groundwater velocity, leach rate, and contaminant retardation. The dominant characteristics of the contaminant concentration distribution are inherited during leaching and modified during transport by dilution, dispersion and decay. For a hypothetical non-decaying, non-dispersing contaminant with no retardation properties, the shape of the source term distribution is governed by the groundwater velocity (dilution) and leach rate. This distribution remains unchanged throughout transport. Under actual conditions, however, dispersion, decay and retardation modify the concentration distribution during both leaching and transport. The amount of dispersion is determined by the distance traveled, but it does have a greater peak-reducing influence on spiked distributions than square-shaped distributions. Decay acts as an overall scaling factor on the concentration distribution. Retardation alters the contaminant travel time and therefore indirectly influences the amount of dilution, dispersion and decay. Simple relationships between individual parameters and groundwater velocity as they influence peak concentration do not exist. For those cases where the source term is not solubility-limited and flow past the waste is independent of regional hydrologic conditions, a threshold concentration occurs at a specific groundwater velocity where the effects of dilution balance those of dispersion and decay

  6. Roles of concrete technology for containment of radioactive contaminants

    International Nuclear Information System (INIS)

    Kitsutaka, Yoshinori; Imamoto, Keiichi

    2014-01-01

    A large amount of radioactive materials was emitted in the environment by the reactor accident at Fukushima Daiichi Nuclear Power Plant. Nuclear debris still remains in the reactor container. An investigative committee was organized in Japan Concrete Institute to study on the containment of radioactive materials and the safe utilization of concrete materials. We have investigated the effect of the hydrogen explosion upon the property of concrete and the transfer of materials into the concrete. We also present the outline of the advice made by Japan Concrete Institute about technologies on the concrete materials for the waterproofing in buildings and for water-shielding walls. (J.P.N.)

  7. A transportable system for radioactivity contaminated water treatment

    International Nuclear Information System (INIS)

    2013-01-01

    Contaminated water treatment system called SARRY for retrieval and recovery of water in operation at the site of Fukushima Daiichi Nuclear Power Plant since August 2011 has been modified by compacting the system size to develop a mobile system SARRY-Aqua that can process Cs-contaminated water (one ton/hour) to the level of 10 Bq/kg. Installing the system in a small container with dimensions conforming to the international standards facilitates transportation by truck and enables the contaminated water treatment occurring in a variety of locations. (S. Ohno)

  8. Method and apparatus for treating liquid contaminated with radioactive particulate solids

    International Nuclear Information System (INIS)

    Hirs, G.

    1976-01-01

    A method and apparatus reduces the amount of radioactive solids resulting from the filtration of particulate contaminants from liquid in a nuclear reactor plant. A filtration system includes a pre-filter comprising a sheet filter medium through which the reactor liquid passes to remove relatively large particulate contaminants for storage or disposal. The reactor liquid is then passed through a bed of granular filter medium to accumulate substantially all the previously non-filtered contaminants and thereby provide a clarified liquid suitable for reuse in the reactor. Backwash liquid is flowed through the granular filter bed to remove and entrain the accumulated contaminants into a slurry which is received by a reservoir where the slurry is maintained quiescently to settle the contaminants. Removal of liquid from the reservoir concentrates the contaminants for storage or further processing, without the necessity of large quantities of filter aids that would increase the quantity of storage-requiring contaminated solids

  9. Modeling the migration of radioactive contaminants in groundwater of in situ leaching uranium mine

    International Nuclear Information System (INIS)

    Li Chunguang; Tai Kaixuan

    2011-01-01

    The radioactive contamination of groundwater from in situ leaching (ISL) of uranium mining is a widespread environmental problem. This paper analyzed the monitor results of groundwater contaminations for a in situ leaching uranium mine. A dynamic model of contaminants transport in groundwater in ISL well field was established. The processes and mechanisms of contaminant transport in groundwater were simulated numerically for a ISL well field. A small quantity of U and SO 4 2- migrate to outside of well field during ISL production stage. But the migration velocity and distance of contaminations is small, and the concentration is low. Contaminants migrate as anomalistic tooth-shape. The migration trend of U and SO 4 2- is consistent. Numerical modeling can provide an effective approach to analyse the transport mechanism, and forecast and control the migration of contaminants in groundwater in ISL well field. (authors)

  10. Radioactivity levels in surface water of lakes around Izmir / Turkey

    International Nuclear Information System (INIS)

    Doyurum, S.; Turkozu, D. A.; Aslani, M. A. A.; Aytas, S.; Eral, M.; Kaygun, A. K.

    2006-01-01

    Radioactivity presents in surface continental waters is mainly due to the presence of radioactive elements in the earth's crust, other artificial radionuclides have appeared due to such human activities as nuclear power plants, nuclear weapons testing and manufacture and use of radioactive sources It is well known that natural radionuclides can be effective as tracers for the different processes controlling the distribution of elements among dissolved and particulate phases in aquatic systems. The detection of high radionuclide concentrations was proposed as a public health problem in several areas and consequently studies into the risks of radionuclides were started in the 2000s. Especially, these radioactive substances in groundwater are an unwanted and involuntary risk factor from natural sources, not artificial sources. These radioactive substances include uranium, radon found in uranium series, and other radioactive substances such as radium and gross alpha. Uranium present in rock, soil, and natural materials, and is found in small quantities in air, water, and food that people always contact. In this project, lake water samples were collected from three lakes around Izmir-Turkey. In surface lake water samples, pH, mV and conductivity values were measured and alkaline content was determined titrimetrically. The uranium concentrations in the lake water samples were measured using uranium analyzer. The radioactivity concentrations related to gross radium isotopes, gross-? and gross-? activities in the surface lake water were determined. The correlation among some parameters for water samples and concentrations of uranium, activity concentration of gross radium isotopes, gross alpha and gross beta radioactivity are also discussed

  11. Verification of radioactive contamination surveys for practical use in biological research centres

    International Nuclear Information System (INIS)

    Macias, M.T.; Requejo, C.; Ruiz, M.; Pina, R.

    2006-01-01

    Unsealed sources are commonly used in science research laboratories. Their manipulation may imply a radioactive contamination hazard. Therefore, adequate and sensitive survey meters must be available, and must have an effective and accurate response to intensity and type of radiation emitted by the used radionuclides to identify and quantify the possible contamination and then be able to avoid any associated or unwanted consequences that may arise. Periodic surveys are performed to show control, any time, any place radioactive contamination is suspected, and to ensure radioisotopes are being used safely. The immediate work areas must be often checked with portable survey monitors, including the entire lab and particularly bench tops, personnel protective equipment or solely designated equipment for isotope use (micro-fuges, water baths, incubators). These are carried out with portable survey instruments like Geiger-Muller tubes, proportional counters and scintillation detectors that provide direct or indirect measurements capabilities. The Radiation Safety Office (R.S.O.) as well as the radioactive compounds working laboratories at the Instituto de Inv. Biomedicas 'A. Sols' (Madrid-Spain) are provided with an adequate radiation measurement instrument. But, before a portable survey instrument is used, several quality checks should be made (batteries, calibration sticker), and the instrument response should be tested with a check source. This paper aims at determining, with a R.S.O. procedure, these surveys working parameters -detection efficiency, calibration factors and minimum detectable activities-, using reference checking sources ( 14 C, 36 Cl, and 90 Sr/ 90 Y) with known radioactivity covering the energy range of beta emitting isotopes used in biological research. No gamma portable monitors have been tested for the R.S.O. has no gamma checking sources. Therefore, 58 beta monitors were tested, obtaining t he efficiency values, the calibration factors (Bq cm-2 s

  12. Consumer risk perception, attitudes and behaviour related to food affected by radioactive contamination

    International Nuclear Information System (INIS)

    Grande, J.

    1999-01-01

    The paper focuses on consumer attitudes to the countermeasures being taken to reduce radioactivity levels in food. Data is collected from a 1998 survey of 1003 Norwegian and 200 Scottish consumers on their fear of experiencing ill health due to radioactive contamination of food products, their risk averting behaviour connected to the Chernobyl accident of 1986, and their willingness to pay (WTP) for untreated food

  13. The system for measurements of radioactive contamination of environment and food in Poland

    International Nuclear Information System (INIS)

    Grabowski, D.; Kurowski, W.

    1990-01-01

    The service for Measurements of Radioactive Contamination comprises a network of 152 measuring stations. They are carrying out continuous measurements of gamma radiation dose rates and radioactivity measurements of 24 hours samples of air (aerosols) and total fallout. On the territory of each province there are selected points for sampling of environmental materials and food. Frequency of sampling depends on material being collected. 1 tab., 2 figs. (A.S.)

  14. An investigation of awareness on the Fukushima nuclear accident and Radioactive contamination

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jeong Chul; Song, Young Ju [Dept. of Consumer Safety, Korea Consumer Agency, Eumseong (Korea, Republic of)

    2016-05-15

    The objective of this study was to investigate Korean people's awareness about impact of the Fukushima nuclear power plant accident in Japan and radioactive contamination caused by it. The respondents of the survey were 600 adults who resided in the Seoul metropolitan area. The survey results show that the majority of respondents were concerned about impact of radiation leakage that might have an effect on our environment. They were worried about radioactive contamination of foodstuffs, particularly fishery products and preferred to acquire information through TV(49.8%) or the Internet(31.3%). Meanwhile, respondents mentioned that the information on the Fukushima nuclear accident and radioactive contamination had not been sufficient and they didn't know well about the follow-up measures of the government on the accident. Most respondents answered that information on radioactive contamination levels and safety of foods and environment was most needed. The results of this study could be useful to enhance awareness on radioactivity and improve risk communication on nuclear power plant accidents.

  15. The reality of radioactive contamination in construction of Taiwan and the treatment concerned

    International Nuclear Information System (INIS)

    Huang Chin-Wang

    2005-01-01

    It has been more than 50 years since Taiwan started the research on the peace application of radioactivity. During the first 20-30 years, it was found that the radioactive contaminated waste steel from atomic power plants was recycled together with general waste steel and was used to make other products including reinforcing bars. It was because the radiation resources ware not carefully controlled and managed. Since 1982, the radioactive contaminated reinforcing bars and buildings were gradually found, as the radiation dose rates were 5 μSv/h and 0.5 μSv/h, respectively. The radioactive nuclide was all Co-60. By August 2003, 1,626 households, 7,824 people's houses were founded to be radioactive contaminated. Furthermore, radiation dose rates higher than 5 μSv/h were measured from 264 of those householders. The government has started to ameliorate this situation and 94.7% of the cases have become normal. The cancer death rate of these people is found to be 0.49% (89 patients in 7,824 people, 39 was dead), and it is 4 times higher than that for general people. In order to solute this pollution problem, the government has made the law to check the radioactivity of all reinforcing bars and to control and manage those radiation resources more carefully. Additionally, there are tax exemption, subsidy, and expropriation with compensation for the polluted buildings. (author)

  16. Long term survey on food pollution and contamination by radioactive fallout in Fukuoka, Japan (1961 - 1976)

    International Nuclear Information System (INIS)

    Morishige, Toshiko; Ishinishi, Noburu; Cho, Tetsuji.

    1977-01-01

    The contamination and the pollution of foodstuffs by radioactive fallout have been investigated since 1961 in Fukuoka city and its suburban area. The results obtained were as follows. 1) Recently, the degree of the contamination of greens by radioactive fallout which fell on the leaves decreased to one thousandth in the early stage of the investigation (1961 - 1962). In the period of the investigation, the remarkable increase of the radioactivity of fallout was observed within a week after the Chinese nuclear bomb explosion in the atmosphere (1st, 2nd, 5th, 12th, 13th, and 15th). The radioactivity was 2 to 300 times higher than the usual level. 2) The radioactivity was not remarkable in vegetables which were washed with soap, but it decreased gradually year by year. The increase of the radioactivity was also observed a few days after the atmospheric nuclear explosion. 3) In milk, there were no remarkable yearly decreases of the radioactivity from the beginning of the investigation, but the seasonal variations of the radioactivity, such as higher in April and May, were observed. 4) The radioactivity in diets based on the standard food production in Japan was the highest in 1967. It decreased gradually from 1967 to 1971 and after that the remarkable variation of the activity was not observed. 5) 137 Cs contamination of foodstuffs has been observed quantitatively by the method of gamma spectrometry, while sometimes 95 Zr- 95 Nb, 103 Ru, and 131 I were also detected from the specimens obtained immediately after the nuclear explosions. (auth.)

  17. Radioactive Cs in the Severely Contaminated Soils Near the Fukushima Daiichi Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kaneko, Makoto; Iwata, Hajime; Shiotsu, Hiroyuki; Masaki, Shota; Kawamoto, Yuji; Yamasaki, Shinya; Nakamatsu, Yuki; Imoto, Junpei; Furuki, Genki; Ochiai, Asumi [Department of Chemistry, Kyushu University, Fukuoka (Japan); Nanba, Kenji [Department of Environmental Management, Faculty of Symbiotic System Science, Fukushima University, Fukushima (Japan); Ohnuki, Toshihiko [Advanced Science Research Center Japan Atomic Energy Agency, Tokai (Japan); Ewing, Rodney C. [Department of Geological Sciences, Center for International Security and Cooperation, Stanford University, Stanford, CA (United States); Utsunomiya, Satoshi, E-mail: utsunomiya.satoshi.998@m.kyushu-u.ac.jp [Department of Chemistry, Kyushu University, Fukuoka (Japan)

    2015-09-01

    Radioactive Cs isotopes ({sup 137}Cs, t{sub 1/2} = 30.07 years and {sup 134}Cs, t{sub 1/2} = 2.062 years) occur in severely contaminated soils within a few kilometer of the Fukushima Daiichi nuclear power plant at concentrations that range from 4 × 10{sup 5} to 5 × 10{sup 7} Bq/kg. In order to understand the mobility of Cs in these soils, both bulk and submicron-sized particles elutriated from four surface soils have been investigated using a variety of analytical techniques, including powder X-ray diffraction analysis, scanning electron microscopy (SEM), transmission electron microscopy (TEM), and analysis of the amount of radioactivity in sequential chemical extractions. Major minerals in bulk soil samples were quartz, feldspar, and minor clays. The submicron-sized particles elutriated from the same soil consist mainly of mica, vermiculite, and smectite and occasional gibbsite. Autoradiography in conjunction with SEM analysis confirmed the association of radioactive Cs mainly with the submicron-sized particles. Up to ~3 MBq/kg of {sup 137}Cs are associated with the colloidal size fraction (<1 μm), which accounts for ~78% of the total radioactivity. Sequential extraction of the bulk sample revealed that most Cs was retained in the residual fraction, confirming the high binding affinity of Cs to clays, aluminosilicate sheet structures. The chemistry of the fraction containing submicron-sized particles from the same bulk sample showed a similar distribution to that of the bulk sample, again confirming that the Cs is predominantly adsorbed onto submicron-sized sheet aluminosilicates, even in the bulk soil samples. Despite the very small particle size, aggregation of the particles prevents migration in the vertical direction, resulting in the retention of >98% of Cs within top ~5 cm of the soil. These results suggest that the mobility of the aggregates of submicron-sized sheet aluminosilicate in the surface environment is a key factor controlling the current Cs

  18. A United States perspective on long-term management of areas contaminated with radioactive materials

    International Nuclear Information System (INIS)

    Jones, C. R.

    2004-01-01

    The US has far-reaching and extensive experience in the long-term management of areas contaminated with radioactive materials. This experience base includes the Dept. of Energy's continued follow-up with Hiroshima and Nagasaki from the 1940's at the Radiological Effects Research Foundation in Hiroshima (Japan)), the long-term management of the Marshall Islands Programme, the clean-up of the US nuclear weapons complex and the ongoing management of accident sites such as in Palomares (Spain)). This paper discusses the lessons learnt and best practices gained from this far-reaching and extensive experience in the long-term management of areas contaminated with radioactive materials. (authors)

  19. Study on the metabolism of contamination of radioactive materials in organism by autoradiographic techniques

    International Nuclear Information System (INIS)

    Zhu Shoupeng; Zhang Lansheng; Kang Baoan

    1988-08-01

    The metabolism of contamination of radioactive materials in organism was studied by diferent types of autoradiographic techniques, such as: (1) in body level by whole-body autoradiography; (2) in organ level by whole-organ autoradiography; (3) in cellular level by microautoradiography; (4) in subcellular level by electron microscopic autoradiography; (5) in combinative form by tissue fixative autoradiography; (6) in ionizing form by freezing autoradiography; (7) for radioactive mateials with two radionuclides by double radionuclide autoradiography; (8) for radioactive materials with low level of radionuclides by fluorescence sensitization autoradiography; (9) in dissociative products by chromatographic autoradiography

  20. Thermal decomposition of woody wastes contaminated with radioactive materials using externally-heated horizontal kiln

    International Nuclear Information System (INIS)

    Iwasaki, Toshiyuki; Kato, Shigeru; Yamasaki, Akihiro; Ito, Takuya; Suzuki, Seiichi; Kojima, Toshinori; Kodera, Yoichi; Hatta, Akimichi; Kikuzato, Masahiro

    2015-01-01

    Thermal decomposition experiments of woody wastes contaminated with radioactive materials were conducted using an externally-heated horizontal kiln in the work area for segregation of disaster wastes at Hirono Town, Futaba County, Fukushima Prefecture. Radioactivity was not detected in gaseous products of thermal decomposition at 923 K and 1123 K after passage through a trap filled with activated carbon. The contents of radioactive cesium ( 134 Cs and 137 Cs) were measured in the solid and liquid products of the thermal decomposition experiments and in the residues in the kiln after all of the experiments. Although a trace amount of radioactive cesium was found in the washing trap during the start-up period of operation at 923 K, most of the cesium remained in the char, including the residues in the kiln. These results suggest that most of the radioactive cesium is trapped in char particles and is not emitted in gaseous form. (author)

  1. Contamination of the air and other environmental samples of the Ulm region by radioactive fission products after the accident of the Chernobyl reactor

    International Nuclear Information System (INIS)

    Krivan, V.; Egger, K.P.; Hausbeck, R.; Schmid, W.

    1986-01-01

    Since April 30, 1986, the radioactivity of the fission products released by the accident of the Chernobyl reactor has been measured in the air of the city of Ulm. The airborne dust samples were collected with flow calibrated samplers on cellulose acetate membrane filters and counted with a high resolution gamma ray spectrometer. Later on, the radioactivity measurements were expanded to other relevant environmental samples contaminated by radioactive atmospheric precipitates including grass, spruce needles, mosses, lichens, various kinds of food, drinking water, asphalt and concrete surface layers, municipal sewage sludge and sewage sludge ash. This paper reports the obtained results. (orig.) [de

  2. Sources to environmental radioactive contamination from nuclear activities in the former USSR

    International Nuclear Information System (INIS)

    Polikarpov, G.G.; Aarkrog, A.

    1993-01-01

    There is three major sites of radioactive environmental contamination in the former USSR: the Cheliabinsk region in the Urals, Chernobyl NPP in Ukraine and Novaya Zemlya in the Arctic Ocean. The first mentioned is the most important with regard to local (potential) contamination, the last one dominates the global contamination. A number of sites and sources are less well known with regard to environmental contamination. This is thus the case for the plutonium production factories at Tomsk and Dodonovo. More information on nuclear reactors in lost or dumped submarines is also needed. From a global point of view reliable assessment of the radioactive run-off from land and deposits of nuclear waste in the Arctic Ocean are in particular pertinent

  3. Immobilization of radioactive strontium in contaminated soils by phosphate treatment

    International Nuclear Information System (INIS)

    Kim, K.H.; Ammons, J.T.

    1990-01-01

    The feasibility of in situ phosphate- and metal- (calcium, aluminum, and iron) solution treatment for 90 Sr immobilization was investigated. Batch and column experiments were performed to find optimum conditions for coprecipitation of 90 Sr with Ca-, Al-, and Fe-phosphate compounds in contaminated soils. Separate columns were packed with artificially 85 Sr-contaminated acid soil as well as 90 Sr-contaminated soil from the Oak Ridge Reservation. After metal-phosphate treatment, the columns were then leached successively with either tapwater or 0.001 M CaCl 2 solution. Most of the 85 Sr coprecipitated with the metal phosphate compounds. Immobilization of 85 Sr and 90 Sr was affected by such factors as solution pH, metal and phosphate concentration, metal-to-phosphate ratio, and soil characteristics. Equilibration time after treatments also affected 85 Sr immobilization. Many technology aspects still need to be investigated before field applications are feasible, but these experiments indicate that phosphate-based in situ immobilization should prevent groundwater contamination and will be useful as a treatment technology for 90 Sr-contaminated sites. 15 refs., 3 figs., 1 tab

  4. Comparative study between radioactive contamination in milk powder by chernobyl accident [137Cs] and natural radioactivity [40K

    International Nuclear Information System (INIS)

    Navarrete, J.M.; Martinez, T.; Cabrera, L.

    2005-01-01

    After the Chernobyl accident in 1986, Mexico imported from an European country 28,000 Tons of contaminated milk powder with the fission product 137 CS. When the contamination was detected, the alarm among the authorities and population spread out very quick and of course the product was retired at once from the foodstuff market. Nevertheless, the public panic grew up in such a manner, that even the way to manage and to dispose safely this material, considered highly dangerous, was largely discussed. Now, about two decades ago from this event, a study has been performed to compare the level of radioactivity due to both radioisotopes present in one saved sample: the artificial contaminant 137 CS, beside the natural, all around present 40 K, in order to evaluate in a more realistic way how risky was the management, possible consumption, and final disposition of this nourishment. This paper considers results obtained within an uncertainty degree equal to ±5%, and set up conclusions by comparing artificial and natural radioactivity present in that contaminated milk powder.

  5. Dispersal of radioactivity by wildlife from contaminated sites in a forested landscape

    Energy Technology Data Exchange (ETDEWEB)

    Garten, C.T. [Oak Ridge National Lab., TN (United States). Environmental Sciences Div.

    1995-12-31

    Oak Ridge National Laboratory (ORNL) is located within the Valley and Ridge Physiographic Province of eastern Tennessee (USA). Wildlife populations have access to some radioactively contaminated sites at ORNL. Contaminated animals or animal nests within the Laboratory`s boundaries have been found to contain {sup 90}Sr or {sup 137}Cs on the order of 10{sup -2}-10{sup 4} Bq g{sup -1} and trace amounts of other radionuclides (including transuranic elements). Animals that are capable of flight and animals with behaviour patterns or developmental life stages involving contact with sediments in radioactive ponds, like benthic invertebrates, present the greatest potential for dispersal of radioactivity. The emigration of frogs and turtles from waste ponds also presents a potential for dispersal of radioactivity but over distances < 5 km. Mud-dauber wasps (Hymenoptera) and swallows (Hirundinidae) may transport radioactive mud for nest building, but also over relatively short distances (0.2-1 km). Movement by small mammals is limited by several factors, including physical barriers and smaller home ranges. Larger animals, like white-tailed deer (Odocoileus virginianus) are potential vectors of radioactivity due to their greater body size, longer life expectancy, and larger home range. Larger animals contain greater amounts of total radioactivity than smaller animals, but tissue concentrations of {sup 137}Cs generally decline with body size. (author).

  6. Analysis of surface contaminants on beryllium and aluminum windows

    International Nuclear Information System (INIS)

    Gmur, N.F.

    1987-06-01

    An effort has been made to document the types of contamination which form on beryllium window surfaces due to interaction with a synchrotron radiation beam. Beryllium windows contaminated in a variety of ways (exposure to water and air) exhibited surface powders, gels, crystals and liquid droplets. These contaminants were analyzed by electron diffraction, electron energy loss spectroscopy, energy dispersive x-ray spectroscopy and wet chemical methods. Materials found on window surfaces include beryllium oxide, amorphous carbon, cuprous oxide, metallic copper and nitric acid. Aluminum window surface contaminants were also examined

  7. Radioactive contamination of animal bones by 90Sr

    International Nuclear Information System (INIS)

    Franic, Z.; Maracic, M.

    1996-01-01

    90 Sr has been regarded as the fission product of great potential hazard to living things because of the unique combination of its 28-y long half-life, the very energetic beta particle of its 90 Y daughter, and its general resemblance to calcium in metabolic processes. Therefore, due to chemical and metabolic similarity to calcium, bone is the critical organ for radioactive isotopes of strontium. The Department of Radiation Protection of the Institute for Medical Research and Occupational Health, has carried out radioactivity measurements of the food chain as part of an extended monitoring programme, since 1963. This includes systematic, long-term measurements of 90 Sr in long bones of some domestic animals (cows and pigs) while data on lamb bones exist for the very beginning of the investigated period, and for the period after the Chernobyl nuclear accident

  8. Characterization of freshwater mosses as indicators of radioactive contamination

    International Nuclear Information System (INIS)

    Beaugelin-Seiller, K.

    1994-01-01

    The necessity of indicators of freshwater contamination has developed the interest for aquatic mosses. From a fundamental point of view, studying the influence of some biotic and abiotic factors has permitted to better know the mechanisms of radionuclides accumulation by these bryophytes. From a radioecological point of view, simulating real cases of water contamination has allowed to give results a very interesting representativeness. The use of mosses as bio-indicators was applied for two in situ experiments, the results of which have been interpreted from those obtained in laboratory. Finally, an approach by a mathematical model has showed that it is possible to have, in a middle term, an evaluation tool of freshwater contamination, based on the radionuclides concentrations measured in aquatic mosses. (author). refs., 57 figs., 24 tabs

  9. Intervention strategies for the recovery of radioactive-contaminated environments

    International Nuclear Information System (INIS)

    Gutierrez, J.; Vazquez, C.

    2000-01-01

    Following an accident with environmental consequences, intervention may be necessary. The type of remedial actions and the strategy required will be dependent upon, inter alia, the phase and conditions within the contaminated scenario. Leaving aside the basic countermeasures (such as confinement, evacuation), which are based on internationally agreed Generic Intervention Levels (GIL's), the paper deals with intervention strategies leading to a return of the contaminated site to as close to normality as possible with the lowest social cost. The reduction of the damage from the existing contamination must be justified and optimised; the best strategy for applying recovery actions must be selected from a set of potential alternatives. A methodology for intervention strategies analysis, developed in the framework of CEC-CHECIR ECP-4 'Decontamination Strategies', is presented together with some examples of application. (author)

  10. Melting-decontamination method for radioactive contaminated metals

    International Nuclear Information System (INIS)

    Uda, Tatsuhiko; Tsuchiya, Hiroyuki; Miura, Noboru; Iba, Hajime.

    1985-01-01

    Purpose: To eliminate uranium components remaining in metals even after the uranium-contaminated metals are melted. Method: Metal wastes contaminated with actinide element or its compound as nuclear fuel substance are melted in a crucible. Molten metals are fallen through a filter disposed at the bottom of the crucible into another receiving crucible. Uranium compounds are still left in the molten metal fallen in the receiving crucible. The residual uranium compounds are concentrated by utilizing the principle of the zone-refining process. That is, a displaceable local-heating heater is disposed to the receiving crucible, by which metals once solidified in the receiving crucible is again heated locally to transfer from solid to molten phase in a quasi-equibilized manner. In this way, by eliminating the end of the metal rod at which the uranium is segregated, the contaminating coefficient can be improved. (Ikeda, J.)

  11. Radiological risk assessment for radioactive contamination at landfill site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

    A limited-scope preliminary assessment of radiological risk has been conducted for a landfill site where radioactive residues resulting from past uranium ore processing operations are present. Potential radiation doses to an individual under different scenarios have been predicted using the RESRAD computer code. The assessment provides useful input to the remedial action planning for the site that is currently underway. 7 refs., 6 figs., 3 tabs

  12. Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

    International Nuclear Information System (INIS)

    Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

    1979-01-01

    The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

  13. Some aspects of radioactive contamination and decontamination of the Chernobyl' NPP accident zone territory

    International Nuclear Information System (INIS)

    Samojlenko, Yu.N.; Nad''yarnykh, G.V.; Teplitskij, A.L.; Shilin, S.A.

    1989-01-01

    Data are presented on the radioactive contamination of the 30-km zone, on the radionuclide (RN) distribution in soils and on the RN migration in grounds. During 1986-1988 were tested over 20 techniques for territory decontamination and were found out the most optimal ones. The first stage of decontamination was removal of an upper contaminated soil layer. The second stage was prolonged chemical fixation of dusting decontaminated soil areas. 3 tabs

  14. Evolution of radioactive dose rates in fresh sediment deposits along coastal rivers draining Fukushima contamination plume

    OpenAIRE

    Evrard, Olivier; Chartin, Caroline; Onda, Yuichi; Patin, Jeremy; Lepage, Hugo; Lef?vre, Ir?ne; Ayrault, Sophie; Ottl?, Catherine; Bont?, Philippe

    2013-01-01

    Measurement of radioactive dose rates in fine sediment that has recently deposited on channel bed-sand provides a solution to address the lack of continuous river monitoring in Fukushima Prefecture after Fukushima Dai-ichi nuclear power plant (FDNPP) accident. We show that coastal rivers of Eastern Fukushima Prefecture were rapidly supplied with sediment contaminated by radionuclides originating from inland mountain ranges, and that this contaminated material was partly exported by typhoons t...

  15. Decontamination methods of the vegetables contaminated with radioactive materials from Fukushima Daiichi Nuclear Power Station accident

    International Nuclear Information System (INIS)

    Nishizawa, Kunihide; Shiba, Kazuhiro

    2011-01-01

    Among agricultural products, vegetables contaminated with radioactive materials were examined to find a practical decontamination method. For spinach, washing by running water or hot water, and by ultrasonic or shower washing were tested. Furthermore, chemical method using detergent acid, alkaline salt was examined. High removal efficiency was obtained for iodine 131 using sodium hydrosulfate. For visual observation, IP imaging and scanning electromagnetic method were used to find spots and plane contamination. (S. Ohno)

  16. Radioactive contamination of the environmental samples in Hanoi in 1989

    International Nuclear Information System (INIS)

    Dang Huy Uyen; Bui Van Loat; Dang Phuong Nam; Cao Anh Duc; Pham Quang Dien; Nguyen Hao Quang

    1990-01-01

    More than 30 environmental samples from soil, paddy, rice, fruits, vegetables and beans, sesame, tea, bananas, fishes at Hanoi markets in 1989 were analysed by gamma ray spectrometry with the low background system for studying natural and artificial radioactive elements. Among several samples from Hanoi in such kind as cultivated soils, tea, dried bamboo shoots, isotope Cs 137 that used be generated from nuclear explosives was found with contents (30 - 1000) x 10 -5 Bq/g; Cs 137 contents in Japanese rice (0.4 - 3) x 10 -5 Bq/g. Cs 137 is radioactive so Cs 137 contents in Vietnamese rice are 300 times higher than Cs 137 contents in Japanese rice but they are hundred times lower than international standard. Among vegetables, fruits, shrimps, fishes in Hanoi markets, artificial isotopes were not found and natural isotopes were few. Even radioactive daughter and granddaughter in uranium series in potatoes were not found. In some samples K 40 was also appeared, for example in cultivated soils (0.78 Bq/g), in dried bamboo shoots (0.73 Bq/g). (author). 2 refs., 3 figs

  17. Monitoring Potential Transport of Radioactive Contaminants in Shallow Ephemeral Channels

    International Nuclear Information System (INIS)

    Miller Julianne J.; Mizell Steve A.; Nikolich George; Campbell Scott A.

    2012-01-01

    The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Nevada Site Office (NSO), Environmental Restoration Soils Activity has authorized the Desert Research Institute (DRI) to conduct field assessments of potential sediment transport of contaminated soil from Corrective Action Unit (CAU) 550, Area 8 Smoky Contamination Area (CA), during precipitation runoff events. CAU 550 includes Corrective Action Sites (CASs) 08-23-03, 08-23-04, 08-23-06, and 08-23-07; these CASs are associated with tests designated Ceres, Smoky, Oberon, and Titania, respectively.

  18. Disposal of the radioactive contaminated soils from the NPP site

    International Nuclear Information System (INIS)

    Matusek, I.; Plsko, J.; Sajtlava, M.; Hulla, J.; Kovacs, T.

    2004-01-01

    Disposal of contaminated soils at site of NPP is one of the most important task within the frame of research and development tasks of the NPP decommissioning. The works within this field can be seen in several areas. Considered soil activity monitoring, observation of its geo-technical and geo-chemical parameters, volume balance, research of the radio nuclides behaviour in the soil and simulation of their influence on the surrounding environment with special emphasis on underground water, project studies and construction of the disposal facility for contaminated soils. This work presents overview of gained results in the mentioned areas of the research and development. (author)

  19. Radioactive Contamination Near Natural Uranium - Graphite - Gas Reactors

    International Nuclear Information System (INIS)

    Chassany, J.; Pouthier, J.

    1967-01-01

    The authors give the results of numerous assessments of contamination in connection with reactors in operation during maintenance; reactors shut down during overhaul and repair work (coolants, exchangers, interior of the tank, etc.) ; and accidents in the cooling circuit and ruptured cladding. They show that, except in special cases, it is mainly activation products that predominate. Moreover, after eight years of operation the points where contamination likely to give considerable dose rates accumulates remain very localized, and there has been no need to reinforce personnel protection measures. (author) [fr

  20. Methods for the calculation of derived working limits for surface contamination by low-toxicity radionuclides

    International Nuclear Information System (INIS)

    Gibson, J.A.B.; Wrixon, A.D.

    1979-01-01

    Surface contamination is often measured as an indication of the general spread of radioactive contamination in a particular place. Derived working limits, (DWLs) for surface contamination provide figures against which to assess the significance of measurements. Derived working limits for surface contamination were first established for use in the nuclear energy industry. They were designed to cope with a wide range of unspecified radionuclides and were therefore based on the assumption that the contamination was due to the presence of the most hazardous radionuclides, e.g. 90 Sr, 210 Pb, 226 Ra and 239 Pu. While this assumption may still be appropriate when the radionuclide mixture is unknown, there are now many specialized uses of particular low-toxicity radionuclides in universities, hospitals and general industry. If it is known that only a particular radionuclide is present, the general DWL can be replaced by a more specific value. The methods for calculating DWLs for some of the more commonly employed low-toxicity radionuclides are described. The exposure pathways considered are (a) external radiation of the skin and inhalation of airborne material from contaminated surfaces in active areas; (b) external irradiation of the skin and ingestion from contaminated skin. Some consideration is given to the effect of the revised dose equivalent limits in the most recent recommendations of ICRP. (author)

  1. Developments in surface contamination and cleaning fundamentals and applied aspects

    CERN Document Server

    Kohli, Rajiv

    2015-01-01

    Developments in Surface Contamination and Cleaning, Vol. 1: Fundamentals and Applied Aspects, Second Edition, provides an excellent source of information on alternative cleaning techniques and methods for characterization of surface contamination and validation. Each volume in this series contains a particular topical focus, covering the key techniques and recent developments in the area. This volume forms the heart of the series, covering the fundamentals and application aspects, characterization of surface contaminants, and methods for removal of surface contamination. In addition, new cleaning techniques effective at smaller scales are considered and employed for removal where conventional cleaning techniques fail, along with new cleaning techniques for molecular contaminants. The Volume is edited by the leading experts in small particle surface contamination and cleaning, providing an invaluable reference for researchers and engineers in R&D, manufacturing, quality control, and procurement specific...

  2. Design and construction of an interceptor system for radioactively contaminated solvent

    International Nuclear Information System (INIS)

    Weiss, T.G. Jr.; Blickwedehl, R.R.

    1991-01-01

    During the conduct of fuel reprocessing operations at the Western New York Nuclear Service Center from 1966 to 1972, the site operator disposed of spent solvent by shallow land burial in the area used for disposal of solid radioactive waste. The spent solvent was placed in twenty-two 3785 liter (1000-gallon) steel tanks which were then placed in eight 6-meter-deep burial holes. With the passage of time groundwater entered the tanks displacing the solvent (a mixture of tributyl phosphate and n-dodecane) and allowing it to enter the surrounding groundwater system. The solvent, which is lighter than water, floated to the surface of the groundwater within the burial holes and began to migrate laterally through cracks caused by weathering. In 1983, after the US Department of Energy (DOE) initiated efforts for the West Valley Demonstration Project (WVDP), trace amounts of solvent were encountered in a monitoring well near the perimeter of the burial area. Since the initial discovery, extensive studies and continued monitoring have been conducted of the solvent migration. In the fall of 1989, this monitoring showed evidence of further on-site migration of the solvent within the disposal area. In response, the DOE authorized West Valley Nuclear Services Company, Inc. (WVNS) to proceed with the design and construction of a trench system to intercept the flow of solvent and prevent it from discharging to nearby streams. Since the solvent and the contaminated groundwater samples taken in the area exhibited high levels of Iodine-129 in an organic complex, it was necessary to construct a pretreatment facility. An important aspect of the trench construction was the management of contaminated soil and construction water. Contaminated soils were placed into storage containers and held for future treatment and disposal. All water pumped from the trench during construction was stored in large bladder tanks, analyzed for hazardous constituents, and upon finding none, was discharged

  3. Calculation of Radioactivity Concentration on Cover Depth of Contaminated Zone for Self-Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Daeseo; Sung, Hyun-Hee; Kim, Gye-Nam; Kim, Seung-Soo; Kim, Ilgook; Han, Gyu Seong; Choi, Jong-Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    We have a lot of uranium contaminated soil and concrete wastes owing to dismantlement of uranium conversion facility. There are several radioactive material disposal methods such as regulation exemption, decontamination and long term storage. It is necessary for us to perform permanent disposal of these wastes. To acquire radiation dose under self-disposal from them, the study on decontamination of some uranium contaminated soil and concrete wastes was performed using electrokinectic-electrodialytic. In this study, we evaluated radiation dose on the cover depth of contaminated zone from the wastes under radiation dose limit using RESRAD Version 6.5. At first, the calculation of the radiation dose on the wastes of contaminated zone are carried out. The second, the cover depth of contaminated zone are analyzed. The application to self-disposal of contaminated zone are also analyzed. To acquire radiation dose under self-disposal from uranium contaminated soil and concrete wastes, we decontaminated some uranium contaminated soil and concrete wastes using electrokinectic-electrodialytic. To perform self-disposal of the quantity (30,000kg) of contaminated zone, the calculating conditions for radiation dose on the cover depth of contaminated zone are as follows. The area of contaminated zone is 10m{sup 2}. The thickness of contaminated zone is 2 m. The cover depth of contaminated zone are analyzed. The application to self-disposal of contaminated zone are also analyzed. Therefore, as the cover depth increases, the uranium concentration has an increasing trend. It realize that the cover depth of contaminated zone is adequate < 2m at the quantity(30,000kg) of contaminated zone. As the cover depth increases, the uranium concentration has a decreasing trend. As the cover depth increases, the radiation dose(residents) has also a decreasing trend.

  4. Multiple methods for assessing the dose to skin exposed to radioactive contamination

    International Nuclear Information System (INIS)

    Dubeau, J.; Heinmiller, B.E.; Corrigan, M.

    2017-01-01

    There is the possibility for a worker at a nuclear installation, such as a nuclear power reactor, a fuel production facility or a medical facility, to come in contact with radioactive contaminants. When such an event occurs, the first order of business is to care for the worker by promptly initiating a decontamination process. Usually, the radiation protection personnel performs a G-M pancake probe measurement of the contamination in situ and collects part or all of the radioactive contamination for further laboratory analysis. The health physicist on duty must then perform, using the available information, a skin dose assessment that will go into the worker's permanent dose record. The contamination situations are often complex and the dose assessment can be laborious. This article compares five dose assessment methods that involve analysis, new technologies and new software. The five methods are applied to 13 actual contamination incidents consisting of direct skin contact, contamination on clothing and contamination on clothing in the presence of an air gap between the clothing and the skin. This work shows that, for the cases studied, the methods provided dose estimates that were usually within 12% (1σ) of each other, for those cases where absolute activity information for every radionuclide was available. One method, which relies simply on a G-M pancake probe measurement, appeared to be particularly useful in situations where a contamination sample could not be recovered for laboratory analysis. (authors)

  5. Characterization of radioactive contaminants and water treatment trials for the Taiwan Research Reactor's spent fuel pool

    International Nuclear Information System (INIS)

    Huang, Chun-Ping; Lin, Tzung-Yi; Chiao, Ling-Huan; Chen, Hong-Bin

    2012-01-01

    Highlights: ► Deal with a practical radioactive contamination in Taiwan Research Reactor spent fuel pool water. ► Identify the properties of radioactive contaminants and performance test for water treatment materials. ► The radioactive solids were primary attributed by ruptured spent fuels, spent resins, and metal debris. ► The radioactive ions were major composed by uranium and fission products. ► Diatomite-based ceramic depth filter can simultaneously removal radioactive solids and ions. - Abstract: There were approximately 926 m 3 of water contaminated by fission products and actinides in the Taiwan Research Reactor's spent fuel pool (TRR SFP). The solid and ionic contaminants were thoroughly characterized using radiochemical analyses, scanning electron microscopy equipped with an energy dispersive spectrometer (SEM-EDS), and inductively coupled plasma optical emission spectrometry (ICP-OES) in this study. The sludge was made up of agglomerates contaminated by spent fuel particles. Suspended solids from spent ion-exchange resins interfered with the clarity of the water. In addition, the ionic radionuclides such as 137 Cs, 90 Sr, U, and α-emitters, present in the water were measured. Various filters and cation-exchange resins were employed for water treatment trials, and the results indicated that the solid and ionic contaminants could be effectively removed through the use of <0.9 μm filters and cation exchange resins, respectively. Interestingly, the removal of U was obviously efficient by cation exchange resin, and the ceramic depth filter composed of diatomite exhibited the properties of both filtration and adsorption. It was found that the ceramic depth filter could adsorb β-emitters, α-emitters, and uranium ions. The diatomite-based ceramic depth filter was able to simultaneously eliminate particles and adsorb ionic radionuclides from water.

  6. On development of systematical recommendations for the appropriate decision-making during relief works of radioactive contaminated areas

    International Nuclear Information System (INIS)

    Bobrov, A.F.; Grachev, M.I.; Andrianov, K.N.; Grinev, M.P.; Savkin, M.N.

    1994-01-01

    The basic principle and decision-making structure on the relief of radioactive contaminated areas on the basic of the cost-benefit analysis are presented. Dose criteria and classification of radioactive contaminated areas are discussed. The examples of multifactorial analysis and hierarchy analysis method are given. 2 tabs

  7. Study of surface potential contamination in radioisotope and radiopharmaceutical production facilities and alternative solutions

    International Nuclear Information System (INIS)

    Suhaedi Muhammad; Rimin Sumantri; Farida Tusafariah; Djarwanti Rahayu Pipin Soedjarwo

    2013-01-01

    Radioisotope and radiopharmaceutical production facilities that exist in their operations around the world in the form of radiological impacts of radiation exposure, contamination of surface and air contamination. Given the number of existing open source in radioisotope and radiopharmaceutical production facility, then the possibility of surface contamination in the work area is quite high. For that to protect the safety and health of both workers, the public and the environment, then the licensee must conduct an inventory of some of the potential that could result in contamination of surfaces in radioisotope and radiopharmaceutical production facilities. Several potential to cause surface contamination in radioisotope and radiopharmaceutical production facilities consist of loss of resources, the VAC system disorders, impaired production facilities, limited resources and lack of work discipline and radioactive waste handling activities. From the study of some potential, there are several alternative solutions that can be implemented by the licensee to address the contamination of the surface so as not to cause adverse radiological impacts for both radiation workers, the public or the environment. (author)

  8. Analysis of Radioactivity Contamination Level of Kartini Reactor Efluen Gas to the Environment

    International Nuclear Information System (INIS)

    Suratman; Purwanto; Aminjoyo, S

    1996-01-01

    The analysis of radioactivity contamination level of Kartini reactor efluen gas to the environment has been done from 13-10-'95 until 8-2-'96. The aim of this research is to determine the radioactivity contamination level on the environment resulted from the release of Kartini reactor efluen gas and other facilities at Yogyakarta Nuclear Research Centre through stack. The analysis methods is the student t-test, the first count factor test and the gamma spectrometry. The gas sampling were carried out in the stack reactor, reactor room, environment and in other room for comparison. Efluen gas was sucked through a filter by a high volume vacuum pump. The filter was counted for beta, gamma and alpha activities. The radioactivity contamination level of the efluen gas passing through the stack to the environment was measured between 0.57 - 1.34 Bq/m3, which was equal to the airborne radioactivity in environment between 0.69 - 1.12 Bq/m3. This radioactivity comes from radon daughter, decay products result from the natural uranium and thorium series of the materials of the building

  9. Assessment of radioecological situation of a site contaminated by technologically enhanced natural radioactivity in Croatia

    International Nuclear Information System (INIS)

    Marovic, G.; Sencar, J.

    1999-01-01

    Radioactivity contamination originating from the coal fired power plant and its waste dumps located in a bay of the Adriatic which is due to geographical characteristics sensitive to any kind of pollution including radioactivity is discussed. Investigations of coal used in regular plant operation and of solid incombustile ash and slag showed increased concentrations of natural radioactivity which may cause general environmental contamination of the bay as well as contamination of the marine environment of this part of Croatian Adriatic. There are two coal slag and ash piles, one of them was closed and covered by soil and the other is a still operating pile. The location of both piles presents a considerable environmental problem: situated close to the seaside, slag and ash are accumulating in the littoral zone and, in the case of operating pile, are being filled up directly into the sea. The aim of this study was to determine the radioactivity level at the ash and slag deposits and to assess the risk of increased radioactivity for the inhabitants of the nearby urban area, for the plant workers and general environment of the bay including the marine environment of this part of the Croatian Adriatic. (author)

  10. Radioactive contamination of the forests of southern Poland and Finland

    International Nuclear Information System (INIS)

    Jasinska, H.; Kozak, K.; Mietelski, J.W.; Barszcz, J.; Greszta, J.

    2004-01-01

    Experimental data of caesium and ruthenium radioactivity in chosen parts of forest ecosystems in Finland and Southern Poland are presented and compared. Measurements were performed with a low-background gamma-rays spectrometer with the Ge(Li) detector. The maximum caesium 137 activity in litter from Poland is 2.5 kBq, in that from Finland 3.9 kBq, in spruce needles it is 0.4 kBq (Poland), 0.9 kBq (Finland) and in fern leaves it is as high as 15.9 kBq per kg of dry mass in one sample from Poland. (author)

  11. GIS-application for analysis of risk of radioactive contamination

    International Nuclear Information System (INIS)

    Baklanov, A.; Rigina, O.; Elyuchnikova, E.; Nazarenko, L.

    1995-01-01

    The main task of the international project Kolanet is the establishment of an information system for quick response on radiation accidents on the Kola peninsula. Along with a monitoring system, the response system includes a system for forecasting of possible consequences of an accident, based on several computer programs. As a first task of the project a data base and a map of the risk objects have been established. The data base includes information on nuclear ships and nuclear facilities, together with data on nuclear explosions, burials and dumping of radioactive wastes. 9 refs., 3 figs

  12. Prevention of radioactive contamination in the manufacture of phosphate fertilizers

    International Nuclear Information System (INIS)

    Romero G, E.T.

    1995-01-01

    In this work was studied the separation of uranium from the phosphate rock to decrease the level of radioactivity in the phosphate fertilizers, this prevents the redistribution of uranium in the environment. The uranium leaching conditions from phosphate rock were estimated using alkaline solutions. The changes in the natural phosphate rock after leaching were studied. The amenability to separate the uranium from phosphate rock with ammonium carbonate / bicarbonate solution was determined. The uranium extraction was approximately 40%. The leaching conditions showed high selectivity for uranium without changes in the ore structure. The bulk ore was not dissolved. (Author)

  13. Treatment techniques for the removal of radioactive contaminants from drinking water

    International Nuclear Information System (INIS)

    Logsdon, Gary S.

    1978-01-01

    Maximum contaminant levels have been set for radioactive contaminants, as required by the Safe Drinking Water Act (PL 93-523). Treatment techniques are available for removing radium and beta-gamma emitters. Presently-used methods of removing radium-226 are precipitative lime softening (80-90% removal) ion exchange softening (95% removal) and reverse osmosis (95% removal). The 5 p Ci/l limit for radium can be met with conventional technology for raw waters in the 5-100 p Ci/l concentration range. Treatment for removal of beta or gamma emitters must be based upon chemical rather than radioactive characteristics of the contaminant. Reverse osmosis can remove a broad spectrum of ions and molecules from water, so it is the process most likely to be used. The maximum contaminant level for beta and gamma radioactivity is an annual dose equivalent to the total body or any organ not to exceed 4 m rem/year. The fate of radionuclides after removal from drinking water should be considered. Presently radium is disposed with other process wastes at softening plants removing radium. Confinement and disposal as a radioactive waste would be very expensive. (author)

  14. The analysis of the level of radioactive contamination of agricultural lands in Mogilev region [Belarus

    International Nuclear Information System (INIS)

    Komleva, S.M.

    2010-01-01

    In the conditions of the Republic of Belarus there was analyzed the present level of radioactive situation and contamination of areas of agricultural companies with radiocesium at in Mogilev region. There were suggested methodical approaches on organizing the use of the lands in such a way as to get the minimum content of radionuclides in the manufactured products

  15. Radioactive contamination of soil-vegetation cover in some southern areas of Semipalatinsk test site

    International Nuclear Information System (INIS)

    Tuleubaev, B.A.; Zharikov, S.K.

    2001-01-01

    The nature of radioactive contamination of meadow-pasture lands in the south of the Semipalatinsk test site (STS) has been studied using experimental data. Individual parameters of radionuclide transport from soil into plants depending upon soil type and sub-type, extent of land use for hay-making and pasturing, and other nature-climatic and anthropogenic factors have been determined. (author)

  16. Development of Radioactive Substance Contamination Diffusion Preventive Equipment for a Hot cell

    International Nuclear Information System (INIS)

    Choo, Yong Sun; Kim, Do Sik; Baik, Seung Je; Yoo, Byung Ok; Kim, Ki Ha; Lee, Eun Pyo; Ahn, Sang Bok; Ryu, Woo Seok

    2009-01-01

    The hot cell of irradiated materials examination facility (IMEF), which has been operating since 1996, is generally contaminated by the radioactive nuclides of irradiated nuclear fuels and structural steels like Cs-137, Co-60, Co-134 and Ru-106. Especially Cs-137 is a main contaminated radioactive isotope which is easily moved here and there due to air flow in the hot cell, water-soluble, extremely toxic, and has a half-life of 30.23 years. To repair or fix the abnormal function of test apparatus installed in the hot cell, the maintenance door, so called a rear door and located at an intervention area, is opened to enter the hot cell inside. In a moment of opening the maintenance door, dirty air diffusion from the hot cell to an intervention area could be occurred in spite of increasing the rpm of exhaust fan to maintain much low under pressure, but an adjacent area to a maintenance door, i.e. intervention area, is very severely contaminated due to the unpredictable air flow. In this paper, the development of the radioactive substance contamination diffusion preventive equipment for a hot cell is studied to prevent dirty and toxic gaseous radioactive nuclides diffusion from a hot cell and installed at an intervention area of IMEF

  17. Mesoscale modelling of radioactive contamination formation in Ukraine caused by the Chernobyl accident

    International Nuclear Information System (INIS)

    Talerko, Nikolai

    2005-01-01

    This work is devoted to the reconstruction of time-dependent radioactive contamination fields in the territory of Ukraine in the initial period of the Chernobyl accident using the model of atmospheric transport LEDI (Lagrangian-Eulerian DIffusion model). The modelling results were compared with available 137 Cs air and ground contamination measurement data. The 137 Cs atmospheric transport over the territory of Ukraine was simulated during the first 12 days after the accident (from 26 April to 7 May 1986) using real aerological information and rain measurement network data. The detailed scenario of the release from the accidental unit of the Chernobyl nuclear plant has been built (including time-dependent radioactivity release intensity and time-varied height of the release). The calculations have enabled to explain the main features of spatial and temporal variations of radioactive contamination fields over the territory of Ukraine on the regional scale, including the formation of the major large-scale spots of radioactive contamination caused by dry and wet deposition

  18. Methodological guide: management of industrial sites potentially contaminated by radioactive substances

    International Nuclear Information System (INIS)

    2001-01-01

    At the request of the Ministries of Health and the Environment, IPSN is preparing and publishing the first version of the methodological guide devoted to managing industrial sites potentially contaminated by radioactive substances. This guide describes a procedure for defining and choosing strategies for rehabilitating such industrial sites. (author)

  19. The forming of the complexes of soil mezofauna in the zone of radioactive contamination

    International Nuclear Information System (INIS)

    Maksimova, S.L.

    2002-01-01

    We carried out the pedobiological research in the different biogeocenoses in the zone of radioactive contamination. Based on the obtained data we can conclude a direct correlation between the viability of the soil invertebrates and the background gamma-radiation intensity. All the facts indicate that soil animal complexes in biogeocenoses exposed to radiation for a long time impact clearly noticeable suppression

  20. Facilities for treatment of radioactive contaminated water in nuclear power plants

    International Nuclear Information System (INIS)

    1981-02-01

    The standard applies to processes applied in facilities for treatment of radioactive contaminated water in nuclear power plants with LWR- and HTR-type reactors. It does not apply to the treatment of concentrates obtained in the decontamination of water. (orig.) [de

  1. Radioautographic studies of the materials obtained from the No. 5 Fukuryu Maru contaminated by radioactive ashes

    Energy Technology Data Exchange (ETDEWEB)

    Kikuchi, T; Akagi, H; Goto, H; Wakisaka, G

    1954-01-01

    The contamination was associated with the presence of small radioactive particles. Although these particles were easily scattered, it was difficult to remove them completely. The particles did not penetrate into the interior of clothes of fine meshes. Decontamination by washing with sea water was not perfect.

  2. Mathematical Modeling of Non-Fickian Diffusional Mass Exchange of Radioactive Contaminants in Geological Disposal Formations

    Directory of Open Access Journals (Sweden)

    Anna Suzuki

    2018-01-01

    Full Text Available Deep geological repositories for nuclear wastes consist of both engineered and natural geologic barriers to isolate the radioactive material from the human environment. Inappropriate repositories of nuclear waste would cause severe contamination to nearby aquifers. In this complex environment, mass transport of radioactive contaminants displays anomalous behaviors and often produces power-law tails in breakthrough curves due to spatial heterogeneities in fractured rocks, velocity dispersion, adsorption, and decay of contaminants, which requires more sophisticated models beyond the typical advection-dispersion equation. In this paper, accounting for the mass exchange between a fracture and a porous matrix of complex geometry, the universal equation of mass transport within a fracture is derived. This equation represents the generalization of the previously used models and accounts for anomalous mass exchange between a fracture and porous blocks through the introduction of the integral term of convolution type and fractional derivatives. This equation can be applied for the variety of processes taking place in the complex fractured porous medium, including the transport of radioactive elements. The Laplace transform method was used to obtain the solution of the fractional diffusion equation with a time-dependent source of radioactive contaminant.

  3. Characterization of freshwater mosses as indicators of radioactive contamination; Caracterisation de mousses dulcaquicoles comme indicateurs de contamination radioactive

    Energy Technology Data Exchange (ETDEWEB)

    Beaugelin-Seiller, K

    1994-12-16

    The necessity of indicators of freshwater contamination has developed the interest for aquatic mosses. From a fundamental point of view, studying the influence of some biotic and abiotic factors has permitted to better know the mechanisms of radionuclides accumulation by these bryophytes. From a radioecological point of view, simulating real cases of water contamination has allowed to give results a very interesting representativeness. The use of mosses as bio-indicators was applied for two in situ experiments, the results of which have been interpreted from those obtained in laboratory. Finally, an approach by a mathematical model has showed that it is possible to have, in a middle term, an evaluation tool of freshwater contamination, based on the radionuclides concentrations measured in aquatic mosses. (author). refs., 57 figs., 24 tabs.

  4. Model for the assessment of surface radionuclide 210 Pb contamination indoors due to presence of radon

    International Nuclear Information System (INIS)

    Mrdja, D.; Bikit, I.; Forkapic, S.

    2009-01-01

    The model is based on the fact that the change of indoor radon concentration, which periodically enters the room, affects only on radioactive decay and the inserted amount of radon in each impact, but not on its diffusion out, i.e. escape from the room. The aim of the model is to assess the surface contamination of the room by lead 210 Pb. (author) [sr

  5. Secondary radioactive contamination of the Black Sea after Chernobyl accident: recent levels, pathways and trends.

    Science.gov (United States)

    Gulin, S B; Mirzoyeva, N Yu; Egorov, V N; Polikarpov, G G; Sidorov, I G; Proskurnin, V Yu

    2013-10-01

    The recent radionuclide measurements have showed that concentrations of the Chernobyl-derived (137)Cs and (90)Sr in the surface Black Sea waters are still relatively high, reaching 56 and 32 Bq m(-3), respectively. This is comparable or even exceeds the pre-Chernobyl levels (∼16 Bq (137)Cs and 22 Bq (90)Sr per m(3) as the basin-wide average values). The measurements have revealed that the Black Sea continues to receive Chernobyl radionuclides, particularly (90)Sr, by the runoff from the Dnieper River. An additional source of (90)Sr and (137)Cs was found in the area adjacent to the Kerch Strait that connects the Black Sea and the Sea of Azov. This may be caused by the inflow of the contaminated Dnieper waters, which come to this area through the North-Crimean Canal. The long-term monitoring of (137)Cs and (90)Sr concentration in the Black Sea surface waters and in the benthic brown seaweed Cystoseira sp., in comparison with the earlier published sediment records of the radionuclides, have showed signs of a secondary radioactive contamination, which has started to increase since the late 1990's. This may be the result of the combined effect of a higher input of radionuclides from the rivers in 1995-1999 due to an increased runoff; and a slow transport of the particulate bound radionuclides from the watersheds followed by their desorption in seawater from the riverine suspended matter and remobilization from the sediments adjacent to the river mouths. Copyright © 2013 Elsevier Ltd. All rights reserved.

  6. Radioactivity of the Bega sediment-case study of a contaminated canal

    International Nuclear Information System (INIS)

    Bikit, I.; Varga, E.; Conkic, Lj.; Slivka, J.; Mrda, D.; Curcic, S.; Zikic-Todorovic, N.; Veskovic, M.

    2005-01-01

    The Bega canal is one among many heavily polluted canals in Vojvodina (the northern province of Serbia and Montenegro). In the framework of the revitalization of this canal, the radionuclide content of the sediment was investigated in order to support the safe deposition after excavation. It was found that, in comparison with the Danube sediment and Vojvodina soil, the Bega sediment is contaminated with 238 U and 137 Cs. The origin of this contamination is discussed. No traces of contamination by nuclear power plants in the region were found, while the presence of technologically enhanced, natural occurring radioactive materials (TENORM) was proved

  7. Improvement of a device for monitoring the contamination of surfaces

    International Nuclear Information System (INIS)

    Barbier, Albert.

    1981-01-01

    The purpose of this invention is to make it possible to monitor the contamination of surfaces by a light weight portable device and enabling the alpha, beta and gamma radiation contamination to be detected. The detection probe which is connected by a single lead to the box is adapted, in each particular case, to the radiation mode emitted by the contaminated surfaces and the box is provided with a special leak-proof socket for connecting the probe and includes means for assessing the counting rate of the radiation given off, depending on the mode of the radiations emitted by the contaminated surfaces and the intensity of the count rate [fr

  8. Device for contaminating laboratory animals by inhalation of radioactive aerosols

    International Nuclear Information System (INIS)

    Lutz, M.; Rouvroy, H.

    1966-01-01

    The contamination enclosure is made up of a sphere to which are attached an aerosol generator, containers adapted to the animals to be used, and the atmospheric sampling system. The sphere is placed in a protective glove-box, the latter being itself protected by an introduction chamber fitted with locking access lids. A detailed description is given of the working principle. As an example, some results are given concerning the contamination of rats by a plutonium oxide aerosol: characteristics of the powder (mean diameter 0.50 μ - standard deviation: 1.4), examination and evolution of the atmospheric activity as a function of time, evaluation of the retention by the lungs by means of histological and autoradiographic examinations. (authors) [fr

  9. Investigation of methods for physical characteristics of atmospheric aerosols and ground dust fractions on radioactive contaminated areas

    International Nuclear Information System (INIS)

    Artem'ev, O.I.; Osintsev, A.Yu.; Gaziev, Ya.I.; Gordeev, S.K.

    2005-01-01

    The paper presents data about current situation and trends to develop investigation methods for physical characteristics of atmospheric aerosols and ground dust fractions that are observed on the former Semipalatinsk Test Site area and adjacent regions. It was considered one of the options for comprehensive collection of radioactive aerosols as fallout within control area of atmospheric contamination and underlying surface with aerosol products of the man-caused dusting on the former STS area to determine rates of 'dry' deposition and ground-based activity concentration contained in these products of radionuclides at different distances from place of dusting. (author)

  10. Environmental safety of the disposal system for radioactive substance-contaminated wastes

    International Nuclear Information System (INIS)

    Oosako, Masahiro

    2012-01-01

    In accordance with the full-scale enforcement of 'The Act on Special Measures concerning the Handling of Radioactive Pollution' in 2012, the collective efforts of entire Japan for dealing with radioactive pollutants began. The most important item for dealing with radioactive pollution is to control radioactive substances that polluted the global environment and establish a contaminated waste treatment system for risk reduction. On the incineration system and landfill disposal system of radioactive waste, this paper arranges the scientific information up to now, and discusses the safety of the treatment / disposal systems of contaminated waste. As for 'The Act on Special Measures concerning the Handling of Radioactive Pollution,' this paper discusses the points of the Act and basic policy, roadmap for the installation of interim storage facilities, and enforcement regulations (Ordinance of the Ministry of the Environment). About the safety of waste treatment system, it discusses the safety level of technical standards at waste treatment facilities, safety of incineration facilities, and safety of landfill disposal sites. (O.A.)

  11. Treatment of Radioactive Contaminated Soil and Concrete Wastes Using the Regulatory Clearance

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Il Sik; Ryu, W. S.; Kim, T. K.; Shon, J. S.; Ahn, S. J.; Lee, Y. H.; Bae, S. M.; Hong, D. S.; Ji, Y. Y.; Lee, B. C

    2008-11-15

    In the radioactive waste storage facilities at the Korea Atomic Energy Research Institute (KAERI) in Daejoen, there are thousands drums of radioactive contaminated soil and concrete wastes. The soil and concrete wastes were generated in 1988 during the decommissioning process of the research reactor and the attached radioactive waste treatment facility which were located in Seoul. The wastes were transported to Daejeon and have been stored since then. At the generation time, the radioactive contamination of the wastes was very low, and the radionuclides in the wastes was Co-60 and Cs-137. As the wastes have been stored for more than 20 years, the radioactivity concentration of the wastes has been decayed to become very extremely low. The wastes are needed to be treated because they take up large spaces at the storage facility. Also by treating the wastes, final disposal cost can be saved. So, the regulatory clearance was considered as a treatment method for the soil and concrete wastes with extremely low radioactivity concentration.

  12. Radioactive contamination of the Shagan river ecosystem components with artificial radionuclides

    International Nuclear Information System (INIS)

    Subbotin, S.B.; Lukashenko, S.N.; Larionova, N.V.; Yakovenko, Yu.Yu.

    2008-01-01

    Full text: The Shagan river is the only surface waterway on the Semipalatinsk Nuclear Test Site territory. It flows along the eastern boundary of the SNTS and is a left-bank tributary of the Irtysh river. The length of the Shagan riverbed is 275 km with an average slope 0.003, which changes considerably from one part of the riverbed to the other. Within the Balapan testing ground the length of the riverbed is about 50 km, and the slope angle is, on average, 0.002. The watershed area of the left-bank part of the testing ground, where testing wells are located, is about 900 km 2 . In 2006 during radio-ecological investigations of the SNTS aquatic environment, scientists determined contamination of the Shagan river with radioactive products of nuclear explosions. The main radioactive pollutant is tritium. Maximal tritium concentration in the river waters (40*10 4 Bq/l) was registered 4.7 km away from the Atomic lake at levels of more than 50 times higher than the maximal permissible level for drinking water. As the distance from the Atomic lake increases, tritium concentration in the Shagan waters considerably decreases, and in the place of its confluence with the Irtysh rivertritium concentration in water becomes 10 Bq/l, which is equal to MPL (maximal permissible level) used for equipment. A complex of scientific investigations including hydrogeological, hydrological and geophysical investigation showed that tritium contamination of the Shagan waters is caused by the discharge of contaminated ground waters from the testing ground Balapan. In 2007 additional investigations of the river ecosystem showed that surface waters of the river in addition to tritium contained 90 Sr, and bottom sedimentations were contaminated with 60 Co, 152 Eu, 154 Eu and 137 Cs. It should be noted that concentration of 90 Sr in water reaches the level comparable with intervention level established by NRB-99 (Radiation Safety Norms) for water and food intake. By the character of tritium and

  13. The Russian Northern Fleet. Sources of radioactive contamination

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, T [Bellona Foundation, Oslo (Norway); Kudrik, I [Bellona Foundation Branch Office, Murmansk (Russian Federation); Nikitin, A [Scientific Production Association ` ` Typhoon` ` , Obninsk (Russian Federation)

    1996-08-01

    The report describes the problems that the Russian Northern Fleet is experiencing with its nuclear powered vessels and with the storage of spent fuel and other nuclear wastes that the operation of these vessels generates. One of the most serious problems is the lack of regional storage and treatment facilities for radioactive waste. This waste is now deposited haphazardly throughout the various navy yards and bases. The establishment of a regional storage facility for spent fuel, radioactive reactor components, and liquid and solid nuclear waste is a necessary precondition for carrying out the decommissioning of nuclear submarines in an environmentally viable manner. A recurrent theme in the report is the lack of civilian control over the different Northern Fleet nuclear facilities. This leads to a disregard of international recommendations with regard to the handling of nuclear waste. Considerable effort has been made to provide comprehensive references in the report, making it clear that the authors sources of information have been open. By presenting this information the authors hope to contribute to increased insight and consequently to help realize necessary national and international measures. 93 refs.

  14. The Russian Northern Fleet. Sources of radioactive contamination

    International Nuclear Information System (INIS)

    Nilsen, T.; Kudrik, I.; Nikitin, A.

    1996-08-01

    The report describes the problems that the Russian Northern Fleet is experiencing with its nuclear powered vessels and with the storage of spent fuel and other nuclear wastes that the operation of these vessels generates. One of the most serious problems is the lack of regional storage and treatment facilities for radioactive waste. This waste is now deposited haphazardly throughout the various navy yards and bases. The establishment of a regional storage facility for spent fuel, radioactive reactor components, and liquid and solid nuclear waste is a necessary precondition for carrying out the decommissioning of nuclear submarines in an environmentally viable manner. A recurrent theme in the report is the lack of civilian control over the different Northern Fleet nuclear facilities. This leads to a disregard of international recommendations with regard to the handling of nuclear waste. Considerable effort has been made to provide comprehensive references in the report, making it clear that the authors sources of information have been open. By presenting this information the authors hope to contribute to increased insight and consequently to help realize necessary national and international measures. 93 refs

  15. Radioactive contamination of food in Slovenia after Chernobyl incident

    Energy Technology Data Exchange (ETDEWEB)

    Milohnoja, M [Veterinary College, Ljubljana (Yugoslavia)

    1986-07-01

    This review of the situation and of measures on veterinary inspection is confined to Slovenia (the most northern republic of SFR Yugoslavia). First analysis of grass and rain-water made on 30 April 1986 showed that Slovenian agricultural superficies are contaminated with J-131 and Cs-137. A program of monitoring grass, rain-water, milk, meat of slaughter animals and game, fish, eggs and other food (vegetables) was made. The degree of contamination of milk with J-131 was very high in the first 10 days of month May, then rapidly lowered. All dairy cattle kept indoors, fed with old feeding stuff and watered with drinking water had milk with less than 60 Bq/l J-131. After 10 May the degree of contamination of milk with Cs-137 and Cs-134 began slowly to increase, but in June to decrease, so that most of the examined samples had less than 100 Bq/l Cs-137 and Cs-134. All milk (from the areas) with more than 200 Bq/l J-131 was sent to milk powder factory or to cheese-dairies. Analyses (made in July and August) of this milk powder showed that J-131 has almost 'disappeared', the content of Cs-137 and Cs-134 varied from 504 to 1150 Bq/l (i.e. 63 to 144 Bq/l in reconstituted milk); in cheese the content of Cs-137 and Cs-134 was lower than 100 Bq/kg.

  16. Radioactive contamination of food in Slovenia after Chernobyl incident

    International Nuclear Information System (INIS)

    Milohnoja, M.

    1986-01-01

    This review of the situation and of measures on veterinary inspection is confined to Slovenia (the most northern republic of SFR Yugoslavia). First analysis of grass and rain-water made on 30 April 1986 showed that Slovenian agricultural superficies are contaminated with J-131 and Cs-137. A program of monitoring grass, rain-water, milk, meat of slaughter animals and game, fish, eggs and other food (vegetables) was made. The degree of contamination of milk with J-131 was very high in the first 10 days of month May, then rapidly lowered. All dairy cattle kept indoors, fed with old feeding stuff and watered with drinking water had milk with less than 60 Bq/l J-131. After 10 May the degree of contamination of milk with Cs-137 and Cs-134 began slowly to increase, but in June to decrease, so that most of the examined samples had less than 100 Bq/l Cs-137 and Cs-134. All milk (from the areas) with more than 200 Bq/l J-131 was sent to milk powder factory or to cheese-dairies. Analyses (made in July and August) of this milk powder showed that J-131 has almost 'disappeared', the content of Cs-137 and Cs-134 varied from 504 to 1150 Bq/l (i.e. 63 to 144 Bq/l in reconstituted milk); in cheese the content of Cs-137 and Cs-134 was lower than 100 Bq/kg

  17. Radioactive contamination processes during 14-21 March after the Fukushima accident: What does atmospheric electric field measurements tell us?

    Science.gov (United States)

    Takeda, M.; Yamauchi, M.; Makino, M.; Owada, T.; Miyagi, I.

    2012-04-01

    Ionizing radiation from the radioactive material is known to increase atmospheric electric conductivity, and hence to decrease vertical downward atmospheric DC electric field at ground level, or potential gradient (PG). In the past, the drop of PG has been observed after rain-induced radioactive fallout (wet contamination) after nuclear tests or after the Chernobyl disaster. After the nuclear accident Fukushima Dai-ichi nuclear power plant (FNPP) that started 11 March 2011, the PG also at Kakioka, 150 km southwest from the FNPP, also dropped a by one order of magnitude. Unlike the past examples, the PG drop was two-stepped on 14 March and 20 March. Both correspond to two largest southward release of radioactive material according to the data from the radiation dose rate measurement network. We compare the Kakioka's PG data with the radiation dose rate data at different places to examine the fallout processes of both on 14 March and on 20 March. The former turned out to be dry contamination by surface wind, leaving a substantial amount of fallout floating near the ground. The latter turned out to be wet contamination by rain after transport by relatively low-altitude wind, and the majority of the fallout settled to the ground at this time. It is recommended that all nuclear power plant to have a network of PG observation surrounding the plant. Takeda, et al. (2011): Initial effect of the Fukushima accident on atmospheric electricity, Geophys. Res. Lett., 38, L15811, doi:10.1029/2011GL048511. Yamauchi, et al. (2012): Settlement process of radioactive dust to the ground inferred from the atmospheric electric field measurement, Ann. Geophys., 30, 49-56, doi:10.5194/angeo-30-49-2012.

  18. The changes in the ecology and physiology of soil invertebrates under influences of radioactive contamination

    International Nuclear Information System (INIS)

    Maksimova, S.

    2006-01-01

    The soil biota is important in building and maintaining soil structure and fertility. Invertebrates are ideal as potential bio indicators of the environmental impact of radioactive contamination: they are widely distributed, often abundant and generally thought of as having low dispersive capacity. They can use as test organisms to detect the side-effects of radioactive contamination. The long-term analysis of ecological and physiological after-effects and biodiversity changes had been studied in the zone of radioactive contamination. Material was collected in the Gomel Region (Belarus), 30 km away from the CNPP in 1986-2004 applying usual pedobiological techniques (soil samples and Barber's pitfall traps) at reference points subjected to radioactive contamination. Soil samples were collected at 0 to 25 cm depth. Samples were taken in locations, which had received considerable radionuclide contaminations. These sites differed in contamination by the composition of fall-out, the forms of radionuclide content in soils, their intake into trophic chains and accumulation in animal and plant organisms. The impacts have been investigated at the: 1) organism and population levels , in terms of individual life histories (birth rate, growth, mortality) or species selection; 2) at the community level: to species diversity and to effects on trophic structure. The invertebrates were determined to species or genera, including juvenile stages. Radioactive contamination caused a distinct decrease in species number; the dominance structure of the community changed. The saprophagous are especially sensitive to environmental disturbances. An initial sharp reduction of animal biodiversity and simplification of the community structure of soil fauna were observed, followed by a long-term process of returning to the initial parameters. Changes in hemolymph, necroses of epithelium and cell structure in connective tissue were registered. The most drastic after-effects were manifested in

  19. Dispersal of radioactivity by wildlife from contaminated sites in a forested landscape

    International Nuclear Information System (INIS)

    Garten, C.T. Jr.

    1992-01-01

    Oak Ridge National Laboratory (ORNL) is located within the Ridge and Valley physiographic province of eastern Tennessee (USA). This area is characterized by deciduous forests dominated by hardwood and mixed mesophytic tree species. Wildlife populations have access to some radioactively contaminated sites at ORNL, and contaminated animals or animal nests within the Laboratory's boundaries have been found to contain on the order of 10 -12 to 10 -6 Ci/g of 90 Sr or 137 Cs, and trace amounts of other radionuclides (including transuranic elements). Theoretical calculations indicate that nanocurie levels of 90 Sr in bone can arise from relatively small amounts (1%) of contaminated browse vegetation in a deer's diet. Measures that have been undertaken at ORNL to curtail the dispersal of radioactivity by animals are briefly reviewed

  20. Study of the correlation between radioactive contamination of milk and forage with strontium 90

    Energy Technology Data Exchange (ETDEWEB)

    Sabo, A; Mezei, I [Joint Inst. for Nuclear Research, Dubna (USSR). Lab. of Neutron Physics

    1978-08-01

    Significant correlation between radioactive contamination of milk and forage is established on the basis of the data mathematic treatment. Contamination of cow milk by /sup 90/Sr is approximately one order less than forage contamination, which testifies to high discrimination ability of cows in biological chain soil-plant-animal-man. Animals have this ability only in relation to /sup 90/Sr. For other radioactive isotopes discirmination factor can differ significantly from the one characteristic of /sup 90/Sr. It is stressed that as a result of high discrimination ability of cows /sup 90/Sr quantity, penetrating into human body from vegetable products is much more, than the one penetrating from milk and milk products.

  1. Model of external exposure of population living in the areas subjected to radioactive contamination

    International Nuclear Information System (INIS)

    Golikov, V.Yu.; Balonov, M.I.

    2002-01-01

    In the paper, we formulated the general approach to assessment of external doses to population living in contaminated areas (the model equation and the set of parameters). The model parameters were assessed on the basis of results of monitoring in the environment, phantom experiments, and social and demographic information obtained on the contaminated areas. Verification of model assessments performed by comparison with measurement results of individual external doses in inhabitants within the thermoluminescent dosimetry method have shown that differences in dose assessments within both methods does not exceed 1.5 times at a confidence level of 95%. In the paper, we present the results illustrating specific features of external dose formation in population living in the areas of Russia subjected to radioactive contamination due to nuclear tests at the Semipalatinsk test site, radioactive releases from the Mayak enterprise, and the Chernobyl accident. (author)

  2. The consequences of radioactive contamination of forest ecosystems due to Chernobyl accident

    International Nuclear Information System (INIS)

    Tikhomirov, F.A.; Shcheglova, A.I.

    1997-01-01

    The effect of forests on the radionuclide primary distribution in different components of the contaminated ecosystems is considered by the example of Chernobyl accident. A basic mathematical model is developed describing 137 Cs biogeochemical cycling under conditions of quasi-steady state radionuclide redistribution in the ecosystem. Forest ecosystems are proved to diminish radionuclide migration in the environment, and forest should be regarded as an important sanitary factor. The contribution of contaminated forests and forest products to the total irradiation dose to local population is estimated. Special countermeasures are elaborated in order to diminish unfavorable consequences of forest radioactive contamination. A long-term dynamics of radioactive situation in the forest ecosystems in forecasted and further studies on the subject are drafted

  3. Some thoughts concerning the radioactive contamination of foodstuffs 10 years after the Chernobyl disaster

    International Nuclear Information System (INIS)

    Szabo, S.A.

    1997-01-01

    Although the Chernobyl disaster happened 10 years ago (26 Apr. 1986), investigation of the radioactive contamination of the environmental is still in the focus of interest. However it can be established that the pollution level in Hungary- like other, from the place of accident rather far located countries - decreased significantly in the food chain in comparison with measured data in May-June, 1986. Practically the present contamination level (e.q. 137 Cs, 90 Sr) since 1989 is the same as it was in the years before the disaster. Since the level of artificial contamination is much less than the natural radioactivity (e.q. 40 K, 226 Ra) of the foodstuffs, the radiation burden caused by the consumed foodstuffs is negligible. (author)

  4. Building classification trees to explain the radioactive contamination levels of the plants; Construction d'arbres de discrimination pour expliquer les niveaux de contamination radioactive des vegetaux

    Energy Technology Data Exchange (ETDEWEB)

    Briand, B

    2008-04-15

    The objective of this thesis is the development of a method allowing the identification of factors leading to various radioactive contamination levels of the plants. The methodology suggested is based on the use of a radioecological transfer model of the radionuclides through the environment (A.S.T.R.A.L. computer code) and a classification-tree method. Particularly, to avoid the instability problems of classification trees and to preserve the tree structure, a node level stabilizing technique is used. Empirical comparisons are carried out between classification trees built by this method (called R.E.N. method) and those obtained by the C.A.R.T. method. A similarity measure is defined to compare the structure of two classification trees. This measure is used to study the stabilizing performance of the R.E.N. method. The methodology suggested is applied to a simplified contamination scenario. By the results obtained, we can identify the main variables responsible of the various radioactive contamination levels of four leafy-vegetables (lettuce, cabbage, spinach and leek). Some extracted rules from these classification trees can be usable in a post-accidental context. (author)

  5. Evolution of radioactive dose rates in fresh sediment deposits along coastal rivers draining Fukushima contamination plume.

    Science.gov (United States)

    Evrard, Olivier; Chartin, Caroline; Onda, Yuichi; Patin, Jeremy; Lepage, Hugo; Lefèvre, Irène; Ayrault, Sophie; Ottlé, Catherine; Bonté, Philippe

    2013-10-29

    Measurement of radioactive dose rates in fine sediment that has recently deposited on channel bed-sand provides a solution to address the lack of continuous river monitoring in Fukushima Prefecture after Fukushima Dai-ichi nuclear power plant (FDNPP) accident. We show that coastal rivers of Eastern Fukushima Prefecture were rapidly supplied with sediment contaminated by radionuclides originating from inland mountain ranges, and that this contaminated material was partly exported by typhoons to the coastal plains as soon as by November 2011. This export was amplified during snowmelt and typhoons in 2012. In 2013, contamination levels measured in sediment found in the upper parts of the catchments were almost systematically lower than the ones measured in nearby soils, whereas their contamination was higher in the coastal plains. We thereby suggest that storage of contaminated sediment in reservoirs and in coastal sections of the river channels now represents the most crucial issue.

  6. Radioactive contaminants in raw materials and foodstuffs of plant origin

    International Nuclear Information System (INIS)

    Stankovicj, S.; Krainchanicj, M.; Stankovicj, A.

    1990-01-01

    The paper concentrates on the results of activity level of radioactive caesium 134 and 137 in the samples of raw materials (barley, oats, soybean, sunflower, pumpkin seed, hops, shreded sugar beet, maize), animal feedstuffs (alfalfa, alfalfa meal, rape, concentrates fed to chickens, pigs or bpvines, dry turnip shreds) and foodstuff of plant origin (lettuce, spinach, cabbage, carrot, celery, cucumber, tomato, olives, sesame). All samples - produced locally on the major part but also including some imported stuff -have been subjected to continuous gamma spectrometry starting with the Chernobyl accident in 1986 through 1989. The highest activity of caesium was recorded in the samples of animal feedstuffs (alfalfa, alfalfa meal, rape) in the years 1986 and 1987. In time, however, the activity tends to drop considerably. (author) 4 refs.; 3 tabs

  7. Analysis of disposition alternatives for radioactively contaminated scrap metal

    International Nuclear Information System (INIS)

    Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

    1997-01-01

    Millions of tonnes of slightly radioactive, scrap iron and steel, stainless steel, and copper are likely to become available as nuclear and other facilities and equipment are withdrawn from service. Disposition of this material is an international policy issue under consideration currently. The major alternatives for managing this material are to either develop a regulatory process for decontamination and recycling that will safeguard human health or to dispose of the scrap and replace the metal stocks. To evaluate the alternatives, we estimate quantities of scrap arising from nuclear power plant decommissioning, evaluate potential price impacts of recycling on regional markets, and assess the health and environmental impacts of the management alternatives. We conclude that decontaminating and recycling the scrap is the superior alternative

  8. Shielding design of radioactive contaminated metal waste packaging

    International Nuclear Information System (INIS)

    Zou Wenhua; Dong Zhiqiang; Yao Zhenyu; Xu Shuhe; Wang Wen

    2015-01-01

    Focusing on the cylindrical source model to calculate γ dose field of waste packages with the relative formulae then derived. By comparing the calculated data of waste packages of type Ⅷ steel box with the monitoring data, it is found that the cylinder source model could accurately reflect the distributions of γ dose of the waste package. Based on the results of the cylindrical source model, a reasonable shielding technology applicable to waste package containers was designed to meet relevant requirements prescribed in standards about the transport and disposal of radioactive materials. The cylinder source model calculated dose distributions for single package in this paper is simple and easy to implement but slightly larger than the monitoring data providing a certain safety margin for the shielding design. It is suitable for radiological engineering practices. (authors)

  9. Dealing with presumed radioactive contamination - a modest proposal

    International Nuclear Information System (INIS)

    Austerlitz, C.; Campos, D.; Villar, H.P.

    2009-01-01

    Reports concerning the occurrence of malignancies and cancer cases among the population caused by the presence of radioactive materials in the environment are not unusual in Brazil. The country's Nuclear Energy Commission, CNEN, is always assigned to launch an investigation in such cases. As a result, human and financial resources are usually committed in operations that, more often than not, end up by discovering that claims are riot related to radiation. This time it was based on some uranium prospecting that has been made near a small town, Lajes Pintadas, RN. Alarmist reports concerning occurrence of stillborn and malformed children and of cancer cases among the adult population, reached the state capital. A team from CNEN was dispatched to Lajes Pintadas to look for the effective presence of environmental radionuclides and to investigate the reported occurrence of malignancies caused by radiation. Due to the well-known dangers related to launching an investigation on a subject so controversial and prone to misinterpretation by the media and the public, a novel approach, both in technical and philosophical terms, was attempted and that proved to be crucial for the success of the whole undertaking: eight years on, no more reports on health problems in Lajes Pintadas were publicised. It was concluded that standard procedures towards claims concerning health problems related to the presence of radioactive materials in the environment need to be re-evaluated. A more realistic approach towards nuclear activities and their risks should be established and the guidelines proposed herein (thorough survey of available data, involvement of local officials and of the affected community, and careful handling of the media) should be closely followed. (author)

  10. Radiation contamination monitors

    International Nuclear Information System (INIS)

    Kato, Tsutomu; Iba, Hiroshi; Sato, Hiroshi

    1999-01-01

    To make sure of no contamination on people, used articles and working uniforms coming out of the radiation controlled area, nuclear power plants are equipped with radioactive contamination monitors. This paper outlines the basic specifications and advantages of our personnel surface contamination monitors to inspect whole-body surface contamination of people coming out, article surface contamination monitors to inspect the surface and inside contamination of used articles brought out, laundry monitors to inspect surface contamination of working uniforms used in the area before and after a wash, and whole-body counters to inspect and measure the internal contamination of a person out of the area. (author)

  11. Phytoremediation of radioactive contaminated soil research and feasibility

    International Nuclear Information System (INIS)

    Li Jianguo; Han Baohua; Ma Binghui; Wang Huijuan; Liang Yong; Liu Jie

    2014-01-01

    Phytoremediation is an emerging environmental control technology with economic, environmental friendliness, etc., but also constrained by a variety of factors, such as difficulties of Hyperaccumulator screening, poor adaptability of plants, longer growing season and low biomass, which greatly limited the development and application of phytoremediation technology. This paper decribed the principles of phytoremediation for U, Sr and Cs contaminated soil, introduced research status involved, briefly nanlyzed the feasibility of phytoremediation techniques combined with the nuclear environmental remediation standards, and proposed suggestions for further researches. (authors)

  12. Radon-induced surface contaminations in neutrinoless double beta decay and dark matter experiments

    International Nuclear Information System (INIS)

    Pattavina, L.

    2011-01-01

    In experiments looking for rare events, like neutrinoless double beta decay (DBD0ν) and dark matter search (DM), one of the main issues is to increase the experimental sensitivity through the material selection and production. The background contribution coming from the materials used for the detector realization has to be minimized. Moreover the net reduction of the background produced by the bulk part of the apparatus has raised concerns about the background contribution coming from the surfaces. Many procedures and techniques were developed during the last years in order to remove and to minimize the presence of possible contaminants on detector surfaces. To succeed in this strategy a big effort was put in defining all possible mechanisms that lead to surface contaminations, as well as specific cleaning procedures, which are able to reduce and control the surface radioactivity. The presence in air and gases of possible radioactive elements that can stick on the detector surfaces can lead to a recontamination process that will vanish all the applied cleaning procedures. Here is presented and analyzed the contribution to the background of rare events experiments like CUORE experiment (DBD0ν) and EDELWEISS experiment (DM) produced by an exposure of their detector components to a big activity of 222 Rn, radioactive daughter isotope from the 238 U chain. (author)

  13. Radioactivity decontamination of materials commonly used as surfaces in general-purpose radioisotope laboratories.

    Science.gov (United States)

    Leonardi, Natalia M; Tesán, Fiorella C; Zubillaga, Marcela B; Salgueiro, María J

    2014-12-01

    In accord with as-low-as-reasonably-achievable and good-manufacturing-practice concepts, the present study evaluated the efficiency of radioactivity decontamination of materials commonly used in laboratory surfaces and whether solvent spills on these materials affect the findings. Four materials were evaluated: stainless steel, a surface comprising one-third acrylic resin and two-thirds natural minerals, an epoxy cover, and vinyl-based multipurpose flooring. Radioactive material was eluted from a (99)Mo/(99m)Tc generator, and samples of the surfaces were control-contaminated with 37 MBq (100 μL) of this eluate. The same procedure was repeated with samples of surfaces previously treated with 4 solvents: methanol, methyl ethyl ketone, acetone, and ethanol. The wet radioactive contamination was allowed to dry and then was removed with cotton swabs soaked in soapy water. The effectiveness of decontamination was defined as the percentage of activity removed per cotton swab, and the efficacy of decontamination was defined as the total percentage of activity removed, which was obtained by summing the percentages of activity in all the swabs required to complete the decontamination. Decontamination using our protocol was most effective and most efficacious for stainless steel and multipurpose flooring. Moreover, treatment with common organic solvents seemed not to affect the decontamination of these surfaces. Decontamination of the other two materials was less efficient and was interfered with by the organic solvents; there was also great variability in the overall results obtained for these other two materials. In expanding our laboratory, it is possible for us to select those surface materials on which our decontamination protocol works best. © 2014 by the Society of Nuclear Medicine and Molecular Imaging, Inc.

  14. Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination

    Directory of Open Access Journals (Sweden)

    Dean Kyne

    2016-07-01

    Full Text Available Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

  15. Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination.

    Science.gov (United States)

    Kyne, Dean; Bolin, Bob

    2016-07-12

    Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP) reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

  16. Radioactive Mapping Contaminant of Alpha on The Air in Space of Repair of Hot Cell and Medium Radioactivity Laboratory in Radio metallurgy Installation

    International Nuclear Information System (INIS)

    Yusuf-Nampira; Endang-Sukesi; S-Wahyuningsih; R-Budi-Santoso

    2007-01-01

    Hot cell and space of acid laboratory medium activity in Radio metallurgy Installation are used for the examination preparation of fuel nuclear post irradiation. The sample examined is dangerous radioactive material representing which can disseminate passing air stream. The dangerous material spreading can be pursued by arranging air stream from laboratory space to examination space. To know the performance the air stream arrangement is hence conducted by radioactive mapping contaminant of alpha in laboratory / space of activity place, for example, medium activity laboratory and repair space. This mapping radioactivity contaminant is executed with the measurement level of the radioactivity from sample air taken at various height with the distance of 1 m, various distance and from potential source as contaminant spreading access. The mapping result indicate that a little spreading of radioactive material happened from acid cupboard locker to laboratory activity up to distance of 3 m from acid cupboard locker and spreading of radioactive contaminant from goods access door of the hot cell 104 to repair space reach the distance of 2 m from goods door access. Level of the radioactive contamination in the space was far under maximum limitation allowed (20 Bq / m 3 ). (author)

  17. Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. Brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling

    International Nuclear Information System (INIS)

    Bachmann, Udo; Biederbick, Walter; Derakshani, Nahid

    2010-01-01

    The recommendation for sampling for prevention of hazards in civil defense is describing the analytics of chemical, biological and radioactive contaminations and includes detail information on the sampling, protocol preparation and documentation procedures. The volume includes a separate brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling.

  18. Methods for studying the radioactive contamination of plants (1963); Methodes d'etude de la contamination radioactive des vegetaux (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R; Jeanmaire, L; Michon, G [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1963-07-01

    The authors first define the doctrine which led to the devising of a method for studying the radioactive pollution of plants, based on the use of simple techniques, having the possibility of being adapted for routine work, and so devised that each stage is proceeded with only if the preceding one justifies it. For each stage a study is effected comparing the results obtained by the use of more exact techniques. The second part describes in detail the techniques used. (authors) [French] Dans une premiere partie lea auteurs definissent la doctrine qui leur a permis d'elaborer une methode d'etude de la pollution radioactive des vegetaux, basee sur l'utilisation de techniques simples, se pretant au travail de serie et concues de telle maniere que chaque etape n'est abordee que si la precedente le justifie. Chaque etape fait l'objet d'une etude qui compare les resultats a ceux obtenue par des techniques plus precises. La deuxieme partie decrit dans le detail les techniques utilisees. (auteurs)

  19. Experimental study of contamination by inhalation of radioactive iodine aerosols. Biological balance; Etude experimentale de la contamination par inhalation d'aerosols d'iode radioactif bilan biologique

    Energy Technology Data Exchange (ETDEWEB)

    Marble, G [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    Several articles have been published concerning research into contamination produced by inhalation of radioactive iodine aerosols in monkeys. Results dealing with the biological balance of this contamination are presented and discussed in this report. (author) [French] L'etude experimentale de la contamination par inhalation d'aerosols d'iode radioactif effectuee chez le singe a fait l'objet de plusieurs publications. Les resultats concernant le bilan biologique de cette contamination sont presentes et discutes dans ce rapport. (auteur)

  20. Investigations on the radioactive contamination of crop plants as a result of hydrogen-bomb detonation. I. Radioactive contamination of crop plants and soil

    Energy Technology Data Exchange (ETDEWEB)

    Mitsui, S; Aso, S; Tensho, K; Kumazawa, K; Miyawaki, K

    1956-01-01

    Samples (74) of leaves, fruits, and other plant parts were collected in May 1955 after being subjected to radioactive fallout between March and May. Counts/min ranged from 1 to 259 on fresh samples. Radiation was strongest on rough-surfaced plants. Lower leaves of trees and grasses under trees showed only week radiation. Washing with H/sub 2/O was very effective but occassionally imperfect, indicating possible intake of fission products through roots and leaves. In August and September plant tissues were ashed extracted with HCl, and /sup 40/K precipitated with NH/sub 4/OH and (NH/sub 4/)/sub 2/CO/sub 3/. Radioactivity ranged from 0 to 22 counts/min/10g dried plant material. No radioactivity was found in roots. Soil samples tested ranged from 2 to 47 counts/min for 5 g dry sample. Poorly drained soils were highest.