Restoration of environments with radioactive residues. Papers and discussions. Proceedings of an international symposium

International Nuclear Information System (INIS)

2000-01-01

After the use of radioactive substances or the application of nuclear energy, radioactive residues may remain in the environment and may give rise to radiation exposure of people. Radioactive residues can originate from several sources. They may be remnants following the termination of a practice such as the decommissioning of a nuclear power plant. Occasionally, residues can derive from the accumulation of radionuclides from normal discharges to the environment of radioactive effluents from practices. Most commonly, they are the result of human activities that have been performed in the past without proper regard for the current international radiation protection requirements. They can also be the consequence of accidents that have released radioactive material to the environment. Radioactive residues are also generated by nature, e.g. in natural deposits of radioactive material found in the earth. Spring waters convey these materials. No matter what the cause of radioactive residues may be, there is the question of whether any restoration of the affected environment is required and, if so, to what extent it should be performed. The International Symposium on Restoration of Environments with Radioactive Residues was devoted to discussing these questions and to fostering the exchange of information on this subject. The Symposium explored five main topics: global overview of the problem; restoration principles and criteria; case studies of actual radiological assessments; a critical analysis of the case studies; and the role of public participation in the decision aiding and decision making processes. The Programme Committee of the Symposium accepted a number of contributed papers and posters for consideration at the Symposium, and these were published shortly before the Symposium. In early 2000, the IAEA released as Working Material a draft, unedited compilation of the present Proceedings Series publication. The present publication, which constitutes the record of

Characterization on incineration residue of radioactive solid wastes

International Nuclear Information System (INIS)

Katoh, Kiyoshi; Hirayama, Katsuyoshi; Kato, Akira.

1989-01-01

Characterization was carried out on incineration residue discharged from the radioactive solid waste incineration unit (capacity, 100 kg/h) in use at the Tokai Research Establishment of Japan Atomic Energy Research Institute (JAERI) to obtain basic data for investigating solidification methods of the residue. The characterized residue was taken from furnace and a primary ceramic filter of the incineration unit which incinerates combustible solid wastes generated at JAERI and the outside organizations. Items of characterization involve a particle size distribution, misplaced materials content, ignition loss, chemical composition and radioactivity of nuclides in the ash. As the results, the size of ash sampled from the furnace distributed a wide range, with about 35∼60 % of ash smaller than 5 mm and about 10∼25 % of massive one larger than 30 mm (max. size: ∼130 mm). The ignition loss was 2∼3 %. The chemical compositions of the ash were mainly SiO 2 , Fe 2 O 3 , CaO and Al 2 O 3 . The specific activities of the ash were about 0.4∼4 x 10 3 Bq/g, and principal contaminants were 60 Co and 137 Cs. (author)

Summary of the engineering assessment of radioactive sands and residues, Lowman Site, Lowman, Idaho

International Nuclear Information System (INIS)

1981-09-01

Ford, Bacon and Davis Utah Inc. has reevaluated the Lowman site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive sands and residues at Lowman, Idaho. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of radioactive sands and residues and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 191,000 tons of radioactive sands, residues, and contaminated soils at the Lowman site constitutes the most significant environmental impact, although windblown radioactive sands and external gamma radiation also are factors

Regulations and decisions in environmental impact assessment of residues radioactivity content

International Nuclear Information System (INIS)

Santos, Adir Janete Godoy dos

2005-01-01

Surveillance of natural radionuclides in the environment did not have high priority over many years compared to that of man-made radioactivity. There is, however, an increasing interest in such measurements since enhanced exposure to natural radioactivity is receiving the same legal weight as any other radiation exposure. In this context the surveillance of technologically enhanced naturally occurring materials, called TENORM becomes important. In Brazil, the industries of processing and chemical compounds production were developed based on mining, milling, transformation and manufacture of ores from sedimentary origin, ignea or metamorphic, which must determine the radioactive composition of the generated solid wastes and residues. Many solids residues stored in the environment has been of environmental concern facing the industries and environmentalists in Brazil as it presents a potential threat to the surrounding environment and to individuals occupationally exposed. Radiation protection regulations have not been applied yet to these industries, as the Brazilian regulatory agency (Comissao Nacional de Energia Nuclear - CNEN) has only recently published a regulatory guide concerning mining and milling of naturally occurring radioactive materials, which may generate enhanced concentrations of radionuclides. With respect to external and internal exposure to natural radionuclides from the solid residues storage, the nuclides of 232 Th, 235 U and 238 U decay chains are relevant, due to the exposure of workers as well as of members of the public. Radionuclides released from a source can be present as ions, molecules, complexes, mononuclear or polynuclear species, colloids, pseudocolloids, particles or fragments varying in size (nominal molecular mass), structure, morphology, density, valence and charge properties. One of the main points in environmental impact assessment is to identify whether the chemical availability is under influence of these speciation

Derivation of residual radioactive material guidelines for uranium in soil at the Former Associate Aircraft Tool and Manufacturing Company Site, Fairfield, Ohio

International Nuclear Information System (INIS)

Faillace, E.R.; Nimmagadda, M.; Yu, C.

1995-01-01

Residual radioactive material guidelines for uranium in soil were derived for the former Associate Aircraft Tool and Manufacturing Company site in Fairfield, Ohio. This site has been identified for remedial action under the U.S. Department of Energy's (DOE's) Formerly Utilized Sites Remedial Action Program (FUSRAP). Single-nuclide and total-uranium guidelines were derived on the basis of the requirement that, after remedial action, the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the site should not exceed (1) 30 mrem/yr for the current-use and likely future-use scenarios or (2) 100 mrem/yr for less likely future-use scenarios. The DOE residual radioactive material (RESRAD) computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation

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

Long-term residual radioactivity in an intermediate-energy proton linac

CERN Document Server

Blaha, J; Silari, M; Vollaire, J

2014-01-01

A new 160 MeV H−H− linear accelerator (LINAC4) is being installed at CERN to replace the present 50 MeV LINAC2 as proton injector of the PS Booster (PSB). During operation, the accelerator components will be activated by the beam itself and by the secondary radiation field. Detailed Monte Carlo simulations, for various beam energies and several decay times, were performed to predict the residual radioactivity in the main accelerator components and to estimate the residual dose rate inside the tunnel. The results of this study will facilitate future dismantling, handling and storage of the activated parts and consequently minimize the radiation dose to involved workers. The component activation was also compared with the exemption limits given in the current Swiss legislation and to the CERN design values, in order to make predictions for the future storage and disposal of radioactive waste. The airborne radioactivity induced by particles escaping the beam dump and the activation of the beam dump cooling w...

Inventory of sites used to develop residual radioactivity criteria

International Nuclear Information System (INIS)

Ronca-Battista, M.; Hardeman, J.C. Jr.

1986-01-01

The US Environmental Protection Agency (EPA), in conjunction with the National Conference of Radiation Control Program Directors (CRCPD), has compiled an inventory of never licensed or otherwise poorly documented sites that may be contaminated with radioactive materials. This effort is in support of the EPA's development of radiation protection criteria for residual radioactivity at decommissioned sites. The inventory will help to establish the range of circumstances for which criteria are needed, as well as the suitability of candidate criteria for actual situations. The information will also be used to develop model sites and facilities for analyzing technical and economic feasibility of residual radioactivity criteria and to assess costs and benefits of alternate criteria. Relevant information about each site, such as radionuclides, waste forms, and quantities present will be included in the inventory when such information is available. The CRCPD has requested that each State radiation control agency furnish the information for the inventory. The inventory supplements the relatively extensive documentation of sites regulated by Federal or State agencies with information on old or unlicensed sites, such as old waste storage sites or radium ore processing facilities

Conditioning of radioactive ash residue in a wave of solid-phase exothermal reactions

International Nuclear Information System (INIS)

Karlina, O.K.; Varlakova, G.A.; Ozhovan, M.I.; Tivanskij, V.M.; Dmitriev, S.A.

2001-01-01

The abilities for utilization of exothermic reaction heat in solid phase for conditioning the ash residue produced as a result of solid radioactive waste burning are analyzed. It is shown that the process of ash residue making monolithic with obtaining the glass-like finish product containing 50-60 mass % of ash residue which meets the requirements for solidified radioactive wastes may be realized without energy supplying from external heat sources. The conditioning is realized in a special crucible furnace-container designed not only for the process conducting but also for subsequent storage or disposal of the finish product [ru

Status policy and criteria for the remediation of sites with radioactive residues in China

International Nuclear Information System (INIS)

Yamin, Z.

1999-01-01

This paper introduces the status policy and criteria for remediation of sites with radioactive residues in China. We deal with the sites in difference patterns according to their circumstances. For the sites related with the decommissioning of the nuclear fuel cycle facilities, the programs for environmental restoration must be reviewed and approved by the State Environmental Protection Administration (SEPA). And the radioactive waste resulting from these facilities should be collected and eventually disposed of at the regional disposal repositories built by the country. For the sites related with use of radionuclides in medicine, research and industry, as well as the small scale extraction and processing of materials containing natural radionuclides, the provincial environmental authority is responsible for approving the restoration projects. These radioactive wastes should finally be sent to the special radioactive waste repositories built by the provincial environmental authorities. So far 21 waste repositories have been built in some provinces. More then 10 sites with radioactive residues have been restored. The standards for general public dose limit and soil residual radionuclides content have been established. (author)

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)

Radioactive wastes and residues: government participation in a control policy

International Nuclear Information System (INIS)

Gelli, Guido

1993-01-01

This paper discusses the politic aspects of the State participation in inspection and control of the radioactive wastes residues with the supervise of Brazilian Nuclear Energy Commission (CNEN), by a national program

The Calculation Of Total Radioactivity Of Kartini Reactor Fuel Element

International Nuclear Information System (INIS)

Budisantoso, Edi Trijono; Sardjono, Y.

1996-01-01

The total radioactivity of Kartini reactor fuel element has been calculated by using ORIGEN2. In this case, the total radioactivity is the sum of alpha, beta, and gamma radioactivity from activation products nuclides, actinide nuclides and fission products nuclides in the fuel element. The calculation was based on irradiation history of fuel in the reactor core. The fuel element no 3203 has location history at D, E, and F core zone. The result is expressed in graphics form of total radioactivity and photon radiations as function of irradiation time and decay time. It can be concluded that the Kartini reactor fuel element in zone D, E, and F has total radioactivity range from 10 Curie to 3000 Curie. This range is for radioactivity after decaying for 84 days and that after reactor shut down. This radioactivity is happened in the fuel element for every reactor operation and decayed until the fuel burn up reach 39.31 MWh. The total radioactivity emitted photon at the power of 0.02 Watt until 10 Watt

Residual radioactivity guidelines for the heavy water components test reactor at the Savannah River Site

International Nuclear Information System (INIS)

Owen, M.B. Smith, R.; McNeil, J.

1997-04-01

Guidelines were developed for acceptable levels of residual radioactivity in the Heavy Water Components Test Reactor (HWCTR) facility at the conclusion of its decommissioning. Using source terms developed from data generated in a detailed characterization study, the RESRAD and RASRAD-BUILD computer codes were used to calculate derived concentration guideline levels (DCGLs) for the radionuclides that will remain in the facility. The calculated DCGLs, when compared to existing concentrations of radionuclides measured during a 1996 characterization program, indicate that no decontamination of concrete surfaces will be necessary. Also, based on the results of the calculations, activated concrete in the reactor biological shield does not have to be removed, and imbedded radioactive piping in the facility can remain in place. Viewed in another way, the results of the calculations showed that the present inventory of residual radioactivity in the facility (not including that associated with the reactor vessel and steam generators) would produce less than one millirem per year above background to a hypothetical individual on the property. The residual radioactivity is estimated to be approximately 0.04 percent of the total inventory in the facility as of March, 1997. According to the results, the only radionuclides that would produce greater than 0.0.1-millirem per year are Am-241 (0.013 mrem/yr at 300 years), C-14 (0.022 mrem/yr at 1000 years) and U-238 (0.034 mrem/yr at 6000 years). Human exposure would occur only through the groundwater pathways, that is, from water drawn from, a well on the property. The maximum exposure would be approximately one percent of the 4 millirem per year ground water exposure limit established by the U.S. Environmental Protection Agency. 11 refs., 13 figs., 15 tabs

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.

Long-term residual radioactivity in an intermediate-energy proton linac

Science.gov (United States)

Blaha, J.; La Torre, F. P.; Silari, M.; Vollaire, J.

2014-07-01

A new 160 MeV H- linear accelerator (LINAC4) is being installed at CERN to replace the present 50 MeV LINAC2 as proton injector of the PS Booster (PSB). During operation, the accelerator components will be activated by the beam itself and by the secondary radiation field. Detailed Monte Carlo simulations, for various beam energies and several decay times, were performed to predict the residual radioactivity in the main accelerator components and to estimate the residual dose rate inside the tunnel. The results of this study will facilitate future dismantling, handling and storage of the activated parts and consequently minimize the radiation dose to involved workers. The component activation was also compared with the exemption limits given in the current Swiss legislation and to the CERN design values, in order to make predictions for the future storage and disposal of radioactive waste. The airborne radioactivity induced by particles escaping the beam dump and the activation of the beam dump cooling water circuit were also quantified. The aim of this paper is to provide data of sufficiently general interest to be used for similar studies at other intermediate-energy proton accelerator facilities.

Long-term residual radioactivity in an intermediate-energy proton linac

International Nuclear Information System (INIS)

Blaha, J.; La Torre, F.P.; Silari, M.; Vollaire, J.

2014-01-01

A new 160 MeV H − linear accelerator (LINAC4) is being installed at CERN to replace the present 50 MeV LINAC2 as proton injector of the PS Booster (PSB). During operation, the accelerator components will be activated by the beam itself and by the secondary radiation field. Detailed Monte Carlo simulations, for various beam energies and several decay times, were performed to predict the residual radioactivity in the main accelerator components and to estimate the residual dose rate inside the tunnel. The results of this study will facilitate future dismantling, handling and storage of the activated parts and consequently minimize the radiation dose to involved workers. The component activation was also compared with the exemption limits given in the current Swiss legislation and to the CERN design values, in order to make predictions for the future storage and disposal of radioactive waste. The airborne radioactivity induced by particles escaping the beam dump and the activation of the beam dump cooling water circuit were also quantified. The aim of this paper is to provide data of sufficiently general interest to be used for similar studies at other intermediate-energy proton accelerator facilities

Derivation of uranium residual radioactive material guidelines for the Elza Gate Site

International Nuclear Information System (INIS)

Cheng, J.J.; Yu, C.; Devgun, J.S.

1991-02-01

Residual radioactive material guidelines for uranium were derived for a large, homogeneously contaminated area at the Elza Gate Site in Oak Ridge, Tennessee. The derivation of the single-nuclide and total uranium guidelines was based on the requirement that the 50-year committed effective dose equivalent to hypothetical individual who lives or works in the immediate vicinity of the Elza Gate Site should not exceed a dose of 100 mrem/yr following decontamination. The DOE residual radioactive guideline computer code RESRAD was used in this evaluation. Four potential scenarios were considered for the site; the scenarios vary with regard to time spent at the site, sources of water used, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded for uranium within 1000 years, provided that the soil concentration of uranium at the Elza Gate Site does not exceed the following levels: 1800 pCi/g for Scenario A (industrial worker: the expected scenario); 4000 pCi/g for Scenario B (recreationist: a plausible scenario); 470 pCi/g for Scenario C (resident farmer using pond water as the only water source: a possible but unlikely scenario); and 120 pCi/g for Scenario D (resident farmer using well water as the only water source: a possible but unlikely scenario). The uranium guideline applies to the total activity concentration of uranium isotopes in their natural activity concentration ratio of 1:1: 0.046. These guidelines are calculated on the basis of a dose of 100 mrem/yr. In setting the actual uranium guideline for the Elza Gate Site, the DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors, such as determining whether a particular scenario is reasonable and appropriate. 10 refs., 3 figs., 7 tabs

Residual radioactive material guidelines: Methodology and applications

International Nuclear Information System (INIS)

Yu, C.; Yuan, Y.C.; Zielen, A.J.; Wallo, A. III.

1989-01-01

A methodology to calculate residual radioactive material guidelines was developed for the US Department of Energy (DOE). This methodology is coded in a menu-driven computer program, RESRAD, which can be run on IBM or IBM-compatible microcomputers. Seven pathways of exposure are considered: external radiation, inhalation, and ingestion of plant foods, meat, milk, aquatic foods, and water. The RESRAD code has been applied to several DOE sites to calculate soil cleanup guidelines. This experience has shown that the computer code is easy to use and very user-friendly. 3 refs., 8 figs

Manual for implementing residual radioactivity guidelines

International Nuclear Information System (INIS)

Gilbert, T.L.; Eckerman, K.F.; Hansen, W.R.; Healy, J.W.; Kennedy, W.E.; Napier, B.A.; Solday, J.K.

1986-01-01

The US Department of Energy (DOE) has recently issued guidelines for residual radioactivity at Formerly Utilized Sites Remedial Action Program (FUSRAP) and remote Surplus Facilities Management Program (SFMP) sites. A manual for implementing these guidelines has been prepared jointly by four DOE laboratories (ANL, LANL, ORNL, and PNL) and is being issued as a supplement to the guidelines. The manual presents procedures and tables for deriving site-specific guidelines for levels of residual radionuclide concentrations in soil that must not be exceeded if a site is to be released for unrestricted use. Guidance for implementing DOE ALARA policy for remedial actions is also included. The concentration factor method is used in the pathway analysis for deriving soil guidelines. The analysis has been structured in a manner that explicitly identifies all of the factors involved. Tables are provided for dose-conversion factors and pathway factors from which environmental transport factors for each radionuclide and pathway may be calculated. The scenarios used for deriving the environmental transport factors and dose conversion factors, and the manner in which the information provided in the manual is used to derive site-specific soil guidelines will be presented

Measurement of residual radioactivity in cooper exposed to high energy heavy ion beam

Energy Technology Data Exchange (ETDEWEB)

Kim, Eunjoo; Nakamura, Takashi [Tohoku Univ., Sendai (Japan). Cyclotron and Radioisotope Center; Uwamino, Yoshitomo; Ito, Sachiko; Fukumura, Akifumi

1999-03-01

The residual radioactivities produced by high energy heavy ions have been measured using the heavy ion beams of the Heavy Ion Medical Accelerator (HIMAC) at National Institute of Radiological Sciences. The spatial distribution of residual radioactivities in 3.5 cm, 5.5 cm and 10 cm thick copper targets of 10 cm x 10 cm size bombarded by 290 MeV/u, 400 MeV/u-{sup 12}C ion beams and 400 MeV/u-{sup 20}Ne ion beam, respectively, were obtained by measuring the gamma-ray activities of 0.5 mm thick copper foil inserted in the target with a high purity Ge detector after about 1 hour to 6 hours irradiation. (author)

Residues of tritium-labeled morantel in lactating dairy cattle

International Nuclear Information System (INIS)

Lynch, M.J.; Mosher, F.R.; Burnett, D.M.; Newby, T.J.

1987-01-01

Residues of morantel and its metabolites were monitored in plasma, urine, and milk of five lactating dairy cattle that received an oral dose of [4,4-pyrimidyl- 3 H 2 ]morantel tartrate at 10 mg/kg. Drug-related radioactivity peaked in plasma at 8 h and in milk by the second milking, postdose, and was 170 and 84 ng/mL, respectively. The fraction of total residues in milk convertible to the marker compound, N-methyl-1,3-propanediamine, was 0.38 on the basis of a comparison of the areas under the curves for total and marker residues. Five days after dosing, 3.9% of the total radioactivity in liver was recovered as tritium water. Total drug-related residues in this target tissue averaged 1.15 μg/g. About half of the drug-related residues in liver was unextractable and was classified by bound

Manual for implementing residual radioactive material guidelines using RESRAD, Version 5.0

Energy Technology Data Exchange (ETDEWEB)

Yu, C.; Zielen, A.J.; Cheng, J.J. [and others

1993-09-01

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material. It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating doses, risks, and guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. Two new pathways, radon inhalation and soil ingestion, have been added to RESRAD. Twenty-seven new radionuclides have also been added, and the cutoff half-life for associated radionuclides has been reduced to six months. Other major improvements to the RESRAD code include the ability to run sensitivity analyses, the addition of graphical output, user-specified dose factors, updated databases, an improved groundwater transport model, optional input of a groundwater concentration and a solubility constant, special models for tritium and carbon-14, calculation of cancer incidence risk, and the use of a mouse with menus.

Manual for implementing residual radioactive material guidelines using RESRAD, Version 5.0

International Nuclear Information System (INIS)

Yu, C.; Zielen, A.J.; Cheng, J.J.

1993-09-01

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material. It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating doses, risks, and guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. Two new pathways, radon inhalation and soil ingestion, have been added to RESRAD. Twenty-seven new radionuclides have also been added, and the cutoff half-life for associated radionuclides has been reduced to six months. Other major improvements to the RESRAD code include the ability to run sensitivity analyses, the addition of graphical output, user-specified dose factors, updated databases, an improved groundwater transport model, optional input of a groundwater concentration and a solubility constant, special models for tritium and carbon-14, calculation of cancer incidence risk, and the use of a mouse with menus

Assessment of radioactive residues arising from radiolabel instability in a multiple dose tissue distribution study in rats

International Nuclear Information System (INIS)

Slatter, J.G.; Sams, J.P.; Easter, J.A.

2003-01-01

Our study objectives were to quantitatively determine the effect of radiolabel instability on terminal phase radioactive tissue residues in a multiple dose tissue distribution study, to quantitatively compare tissue residue artifacts (non drug-related radioactivity) from two chemically-distinct radiolabel locations, and to conduct a definitive multiple dose tissue distribution study using the better of the two radiolabeled compounds. We compared the excretion and tissue distribution in rats of [ 14 C]linezolid, radiolabeled in two different locations, after 7 consecutive once daily [ 14 C] oral doses. The radiolabels were in the acetamide (two carbon) and oxazolidinone (isolated carbon) functional groups. Terminal phase tissue residue and excretion data were compared to data from rats dosed orally with [ 14 C]sodium acetate. Drug-related radioactivity was excreted rapidly over 24 h. After a single dose, the acetamide and oxazolidinone radiolabel sites both gave 3% of dose as exhaled 14 CO 2 . After 7 daily [ 14 C] oral doses, terminal phase radioactive tissue residues were higher from the acetamide radiolabel, relative to the oxazolidinone radiolabel, and were primarily not drug-related. In the definitive tissue distribution study, low concentrations of drug-related radioactivity in skin and thyroid were observed. We conclude that although small amounts of radiolabel instability do not significantly affect single dose tissue radioactivity C max and area under the curve (AUC), artifacts arising from radiolabel instability can prolong the apparent terminal phase half life and complicate study data interpretation. When possible, it is always preferable to use a completely stable radiolabel site. (author)

Assessment of radioactive residues arising from radiolabel instability in a multiple dose tissue distribution study in rats

Energy Technology Data Exchange (ETDEWEB)

Slatter, J.G. [Pharmacia Corp., Peapack, NJ (United States); Sams, J.P.; Easter, J.A. [Pharmacia Corp., Kalamazoo, MI (United States)] [and others

2003-05-01

Our study objectives were to quantitatively determine the effect of radiolabel instability on terminal phase radioactive tissue residues in a multiple dose tissue distribution study, to quantitatively compare tissue residue artifacts (non drug-related radioactivity) from two chemically-distinct radiolabel locations, and to conduct a definitive multiple dose tissue distribution study using the better of the two radiolabeled compounds. We compared the excretion and tissue distribution in rats of [{sup 14}C]linezolid, radiolabeled in two different locations, after 7 consecutive once daily [{sup 14}C] oral doses. The radiolabels were in the acetamide (two carbon) and oxazolidinone (isolated carbon) functional groups. Terminal phase tissue residue and excretion data were compared to data from rats dosed orally with [{sup 14}C]sodium acetate. Drug-related radioactivity was excreted rapidly over 24 h. After a single dose, the acetamide and oxazolidinone radiolabel sites both gave 3% of dose as exhaled {sup 14}CO{sub 2}. After 7 daily [{sup 14}C] oral doses, terminal phase radioactive tissue residues were higher from the acetamide radiolabel, relative to the oxazolidinone radiolabel, and were primarily not drug-related. In the definitive tissue distribution study, low concentrations of drug-related radioactivity in skin and thyroid were observed. We conclude that although small amounts of radiolabel instability do not significantly affect single dose tissue radioactivity C{sub max} and area under the curve (AUC), artifacts arising from radiolabel instability can prolong the apparent terminal phase half life and complicate study data interpretation. When possible, it is always preferable to use a completely stable radiolabel site. (author)

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

The IAEA's functions and policies on the restoration of environments with radioactive residues

International Nuclear Information System (INIS)

Gonzalez, A.J.

2000-01-01

A global regime for the regulation of radiation sources is being established by the international community. A general agreement has already been achieved in the current international radiation protection recommendations, which should be resolutely applied. Protection against radioactive residues delivering relatively low level radiation doses can be regulated within the framework provided by the growing international regime based on these recommendations and composed of international conventions, safety standards and provisions for the application of these standards. It is to be noted, however, that the international safety regime is not more than a provider of a decision aiding mechanism based mainly on a global scientific consensus on radiation protection. Its outcome can only serve as input to a final (usually wider) decision making process, which may take into account societal and other concerns at a national, or even local, level. Many situations involving radioactive residues arise in the human habitant and, therefore, the decision making process should involve the participation of all relevant stakeholders in that habitant, rather than radiation protection specialists alone. The combination of decision aiding regulations based on the international regime being catalyzed under the IAEA and a decision making process that takes account of local circumstances and stakeholders' interests should prevent the current problems in the regulation of radioactive residues and in the restoration of the affected environments

Derivation of guidelines for uranium residual radioactive material in soil at the B ampersand T Metals Company site, Columbus, Ohio

International Nuclear Information System (INIS)

Kamboj, S.; Nimmagadda, Mm.; Yu, C.

1996-01-01

Guidelines for uranium residual radioactive material in soil were derived for the B ampersand T Metals Company site in Columbus, Ohio. This site has been identified for remedial action under the US Department of Energy's (DOE's) Formerly Utilized Sites Remedial Action Program (FUSRAP). Single-nuclide and total-uranium guidelines were derived on the basis of the requirement that following remedial action, the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the site should not exceed a dose constraint of 30 mrem/yr for the current use and likely future use scenarios or a dose limit of 100 n-mrem/yr for less likely future use scenarios. The DOE residual radioactive material guideline computer code, RESRAD, was used in this evaluation. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines. Three scenarios were considered; each assumed that for a period of 1,000 years following remedial action, the site would be used without radiological restrictions. The three scenarios varied with regard to the type of site use, time spent at the site by the exposed individual, and sources of food and water consumed. The evaluations indicate that the dose constraint of 30 mrem/yr would not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1,000 years, provided that the soil concentration of total uranium (uranium-234, uranium-235, and uranium-238) at the B ampersand T Metals site did not exceed 1, I 00 pCi/g for Scenario A (industrial worker, current use) or 300 pCi/g for Scenario B (resident with municipal water supply, a likely future use). The dose limit of 100 mrem/yr would not be exceeded at the site if the total uranium concentration of the soil did not exceed 880 pCi/g for Scenario C (resident with an on-site water well, a plausible but unlikely future use)

Derivation of residual radioactive material guidelines for uranium in soil at the Middlesex Sampling Plant Site, Middlesex, New Jersey

International Nuclear Information System (INIS)

Dunning, D.E.

1995-02-01

Residual radioactive material guidelines for uranium in soil were derived for the Middlesex Sampling Plant (MSP) site in Middlesex, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy. The site became contaminated from operations conducted in support of the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC) between 1943 and 1967. Activities conducted at the site included sampling, storage, and shipment of uranium, thorium, and beryllium ores and residues. Uranium guidelines for single radioisotopes and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the MSP site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The RESRAD computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation. Four scenarios were considered for the site. These scenarios vary regarding future land use at the site, sources of water used, and sources of food consumed

Radiological survey of the radioactive sands and residues at Lowman, Idaho

International Nuclear Information System (INIS)

Haywood, F.F.; Burden, J.E.; Ellis, B.S.; Loy, E.T.; Shinpaugh, W.H.

1980-08-01

No uranium ore milling was performed at the Lowman site, which is located approximately 0.8 km northeast of the town of Lowman, Idaho. Nevertheless, approximately 80,000 metric tons of radioactive sands and residues from upgrading of heavy minerals by physical processing methods remain on the site grounds. Measurements of external gamma radiation 1 m above the surface showed exposure rates up to 2.4 mR/hr on site, but the exposure rate off site quickly dropped to the background level in all directions. Analysis of surface soil and sediment samples for 226 Ra and 232 Th indicated a limited spread of radioactive material

SU-E-T-534: Level of Residual Radioactivity of Activated Parts of a Decommissioned Cyclotron

International Nuclear Information System (INIS)

Choi, HHF; Leung, TM; Chiu, TL; Yang, B; Wu, PM; Cheung, KY; Yu, SK

2015-01-01

Purpose: CTI cyclotron RDS-111 was used at the Hong Kong Sanatorium and Hospital (HKSH) to produce radiopharmaceuticals and radioactive tracers for diagnostic scans between 1999 and 2007. During the operation, some machine components became radioactive by activation. For the safety of staff, decommissioning took place in 2009, two years after the cyclotron had stopped operation. This study investigates the residual radioactivity and radionuclides found in different cyclotron components in 2014 in compliance with the local regulations in Hong Kong for transfer of radioactive waste. Methods: A representative sample of each part was counted using a high-purity germanium detector (manufacturer: ORTECT) for at least four hours. GammaVision, a multichannel analyzer software, was used to identify the radionuclides found in the cyclotron components, as well as the associated activities. A standard library and a Mariscotti peak search algorithm were used to identify the present radionuclides. Only radionuclides with half-life greater than 180 days were considered. Results: Among the components, the Havar target foil has the highest specific activity ((4.6±0.6)×10 2 Bq/g), with Co-60 being the most prominent ((3.8±0.5)×10 2 Bq/g). The total activity of the target foil, however, is still low due to its small mass of 0.04 g. Radioisotopes Mn-54 (46±6 Bq/g), Na-22 (6.8±0.8 Bq/g), Co-57 (7.3±0.9 Bq/g), and Fe-59 (6.0±0.9 Bq/g) have also been detected in the target foil. The target window holder and the vacuum window register a specific activity of 88.3±0.6 Bq/g and 48.6±0.1 Bq/g, respectively. Other components, such as the collimator, the target tube, the valve body and the beamline, are also found with trace amounts of radionuclides. Conclusion: Even seven years after the cyclotron had stopped operation, some components still exhibited residual radioactivity from activation exceeding the IAEA clearance levels. Special consideration for radiological protection may need

Influence of residual oxygen-15-labeled carbon monoxide radioactivity on cerebral blood flow and oxygen extraction fraction in a dual-tracer autoradiographic method.

Science.gov (United States)

Iwanishi, Katsuhiro; Watabe, Hiroshi; Hayashi, Takuya; Miyake, Yoshinori; Minato, Kotaro; Iida, Hidehiro

2009-06-01

Cerebral blood flow (CBF), cerebral metabolic rate of oxygen (CMRO(2)), oxygen extraction fraction (OEF), and cerebral blood volume (CBV) are quantitatively measured with PET with (15)O gases. Kudomi et al. developed a dual tracer autoradiographic (DARG) protocol that enables the duration of a PET study to be shortened by sequentially administrating (15)O(2) and C(15)O(2) gases. In this protocol, before the sequential PET scan with (15)O(2) and C(15)O(2) gases ((15)O(2)-C(15)O(2) PET scan), a PET scan with C(15)O should be preceded to obtain CBV image. C(15)O has a high affinity for red blood cells and a very slow washout rate, and residual radioactivity from C(15)O might exist during a (15)O(2)-C(15)O(2) PET scan. As the current DARG method assumes no residual C(15)O radioactivity before scanning, we performed computer simulations to evaluate the influence of the residual C(15)O radioactivity on the accuracy of measured CBF and OEF values with DARG method and also proposed a subtraction technique to minimize the error due to the residual C(15)O radioactivity. In the simulation, normal and ischemic conditions were considered. The (15)O(2) and C(15)O(2) PET count curves with the residual C(15)O PET counts were generated by the arterial input function with the residual C(15)O radioactivity. The amounts of residual C(15)O radioactivity were varied by changing the interval between the C(15)O PET scan and (15)O(2)-C(15)O(2) PET scan, and the absolute inhaled radioactivity of the C(15)O gas. Using the simulated input functions and the PET counts, the CBF and OEF were computed by the DARG method. Furthermore, we evaluated a subtraction method that subtracts the influence of the C(15)O gas in the input function and PET counts. Our simulations revealed that the CBF and OEF values were underestimated by the residual C(15)O radioactivity. The magnitude of this underestimation depended on the amount of C(15)O radioactivity and the physiological conditions. This underestimation

Investigation of total α and total β radioactive level of environment mediator in the Dushu lake campus of Suzhou university

International Nuclear Information System (INIS)

Jiang Wenhua; Wan Jun; Liu Li; He Chao; Tang Hua; Tu Yu

2008-01-01

Objective: To get the message of natural radioactive level in the Dushu lake cam- pus of Suzhou university. Methods: Different types of water, soil and food in this region were collected, and then the level of total α and total β radioactivity of the sample was investigated applying model BH1216 equipment which measuring was used for low background total α and β radioactivity. Results: Total α in city water, surface water and soil were 0.061 Bq/L, 0.104 Bq/L, 1708 Bq/kg respectively, total β were 0.183 Bq/L, 0.319 Bq/L, 780 Bq/kg respectively, total α in chive, potato, water bamboo, pork, fish were 1.83, 2.36, 1.84, 3.40, 3.76 Bq/kg respectively, total α of Fish bone was at infra-monitoring lower limit, total β in them were 70.81, 96.71, 60.63, 86.20, 97.51, 73.94 Bq/kg respectively. Conclusion: The results of the investigation display that the total radioactivity in drinking water and food don't exceed limits, in surface water and soil is at normal natural background. It can be concluded that this region has not been polluted by the artificial radioactivity and the environment of human habitation is healthy and safe. (authors)

Evaluation and analysis of the residual radioactivity for the 15UD Pelletron accelerator facility

International Nuclear Information System (INIS)

Sonkawade, R. G.

2007-01-01

For the assessment of radiological impact of the accelerators, it will be better to have the documented information on activation of metal parts of the accelerator components. It is very much essential to get reliable data on these subjects. During acceleration of light ion, the residual radioactivity in the accelerator facility was found near the Analyzing Magnet, single slit, Beam Profile Monitors (BPM), Faraday Cups (FC), bellows, beginning of switching magnet bellows, at the target and the ladder. Study with HPGE detector gives an insight of the formation of the short or long lived radionuclides. The different targets used in the light ion experiment were also monitored and proper decommissioning and decontamination steps were followed. This paper presents the data of residual radioactivity in the 15UD Pelletron accelerator infrastructure. (author)

Derivation of uranium residual radioactive material guidelines for the Shpack site

International Nuclear Information System (INIS)

Cheng, J.J.; Yu, C.; Monette, F.; Jones, L.

1991-08-01

Residual radioactive material guidelines for uranium were derived for the Shpack site in Norton, Massachusetts. This site has been identified for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). The uranium guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Shpack site should not exceed a dose of 100 mrem/yr following decontamination. The DOE residual radioactive material guideline computer code, RESRAD, which implements the methodology described in the DOE manual for implementing residual radioactive material guidelines, was used in this evaluation. Three potential scenarios were considered for the site; the scenarios vary with regard to time spent at the site, sources of water used, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1000 years, provided that the soil concentration of combined uranium (uranium-234 and uranium-238) at the Shpack site does not exceed the following levels: 2500 pCi/g for Scenario A (recreationist: the expected scenario); 1100 pCi/g for Scenario B (industrial worker: a plausible scenario); and 53 pCi/g for Scenario C (resident farmer using a well water as the only water source: a possible but unlikely scenario). The uranium guidelines derived in this report apply to the combined activity concentration of uranium-234 and uranium-238 and were calculated on the basis of a dose of 100 mrem/yr. In setting the actual uranium guidelines for the Shpack site, DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors, such as whether a particular scenario is reasonable and appropriate. 8 refs., 2 figs., 8 tabs

Determinations of total residue, total oxide and density of high-level liquid waste (HLLW) by gravimetric method

International Nuclear Information System (INIS)

Li Yun; Gao Yueying; Yang Ming; Jin Liyun

1992-01-01

Gravimetric method for determination of total residue, total oxide and density of HLLW is developed. An aliquot of the original HLLW solution is piped on to the small quartz disc and put into the mini muffle furnace carefully. It is first heated to below 100 degree C (for 1.5 hours to remove the free water, and then heated to 180 degree C for 2 hours to remove the crystal water in a furnace. The total residue is weighed at room temperature. The precision is better than 3% for the determination of total residue and total oxide. An aliquot of the original HLLW solution is piped into the weighing bottle and weighed. The precision is better than 1%

Derivation of residual radioactive material guidelines for the Laboratory for Energy-Related Health Research site

International Nuclear Information System (INIS)

Chapman, T.E.

1993-11-01

Residual radioactive material guidelines were derived for the Laboratory for Energy-Related Health Research (LEHR) Environmental Restoration (ER) site in Davis, California. The guideline derivation was based on a dose limit of 100 mrem/yr. The US Department of Energy (DOE) residual radioactive material guideline computer code was used in this evaluation. This code implements the methodology described in the DOE manual for implementing residual radioactive material guidelines. Three potential site utilization scenarios were considered with the assumption that following ER action, the site will be used without radiological restrictions. The defined scenarios vary with regard to use of the site, time spent at the site, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded, provided that the soil concentrations of these radionuclides at the LEHR site do not exceed the scenario-specific values calculated by this study. Except for the extent of the contaminated zone (which is very conservative), assumptions used are as site-specific as possible, given available information. The derived guidelines are single- radionuclide guidelines and are linearly proportional to the dose limit used in the calculations. In setting the actual residual soil contamination guides for the LEHR site, DOE will apply the as low as reasonably achievable policy to the decision-making process, along with other factors such as whether a particular scenario is reasonable and appropriate, as well as using site-specific inputs to computer models based on data not yet fully determined

ENTRIA 2014. Memorandum on the disposal of high-level radioactive residuals

International Nuclear Information System (INIS)

Roehlig, Klaus-Juergen; Walther, Clemens; Bach, Friedrich-Wilhelm

2014-01-01

The memorandum on the disposal of high-level radioactive residuals covers the following issues: description of the problem: a ''wicked problem'', risks and NIMBY, the site selection law, international boundary conditions; disposal strategy and types of facilities: safety and reversibility, long-term surface storage, deep storage; risk and safety; procedural justice and the site selection process; social innovations and the requirement of long-term institutions; conclusion - central stress fields.

Residual radioactivity in the vicinity of formerly utilized MED/AEC sites

International Nuclear Information System (INIS)

Haywood, F.F.; Goldsmith, W.A.

1980-01-01

As demand for uranium and thorium was accelerated during the 1940's, services of chemical and metallurgical firms and major research facilities were contracted as needed by the Manhattan Engineer District (MED). A lack of documentation of the radiological status at the time contracts were terminated at these facilities led the Department of Energy (DOE), and its predecessor the Energy Research and Development Administration (ERDA), to develop a major radiological resurvey program to fill this information void. A combination of aerial and ground-level radiological monitoring teams were utilized to identify and assess off-site radioactivity. Results from comprehensive aerial surveys provide the approximate areal extent of elevated radiation levels on the ground. These aerial survey results led to two types of ground-level surveys: (1) gamma-ray scanning on foot or from a motorized vehicle (mobile lab based system) to pinpoint the location of residual radioactivity; and (2) compehensive radiological surveys to determine the amount and type of materials present on specific parcels of private and public property identified during the scanning. This type of investigation was initiated in 1978 and has been successful in identifying and assessing the potential radiation hazard from property on which materials bearing natural radioactivity have been found. This paper contains a description of the techniques used to find and evaluate radioactive material displaced outside the boundaries of a formerly utilized site

(238)U and total radioactivity in drinking waters in Van province, Turkey.

Science.gov (United States)

Selçuk Zorer, Özlem; Dağ, Beşir

2014-06-01

As part of the national survey to evaluate natural radioactivity in the environment, concentration levels of total radioactivity and natural uranium have been analysed in drinking water samples. A survey to study natural radioactivity in drinking waters was carried out in the Van province, East Turkey. Twenty-three samples of drinking water were collected in the Van province and analysed for total α, total β and (238)U activity. The total α and total β activities were counted by using the α/β counter of the multi-detector low background system (PIC MPC-9604), and the (238)U concentrations were determined by inductively coupled plasma-mass spectrometry (Thermo Scientific Element 2). The samples were categorised according to origin: tap, spring or mineral supply. The activity concentrations for total α were found to range from 0.002 to 0.030 Bq L(-1) and for total β from 0.023 to 1.351 Bq L(-1). Uranium concentrations ranging from 0.562 to 14.710 μg L(-1) were observed in drinking waters. Following the World Health Organisation rules, all investigated waters can be used as drinking water.

Report on residual radioactive materials on public or acquired lands of the United States

Energy Technology Data Exchange (ETDEWEB)

None

1979-07-01

This report identifies sites located on public or acquired lands of the United States containing residual radioactive materials and other radioactive waste (excluding waste resulting from the production of electric energy) and was developed in accordance with the provisions of Section 114(b) of Public Law 95-604, "Uranium Mill Tailings Radiation Control Act of 1978," enacted on November 8, 1978. Additionally, the report specifies which Federal agency has jurisdiction over such sites and, where appropriate data were available, provides a description of the radiological status of each of the sites reported. For purpose of providing a timely report t o t h e Congress, a termination date of May 31, 1979 was established for the receipt, correlation, and analysis of the input data. As of this date, residual radioactive materials and other radioactive waste have been identified by six Federal agencies at 48 sites throughout the United States. Table 1 on page vi provides a summary listing of the number of sites under the jurisdiction of each of these reporting agencies. A cross listing in tabular form by affected state is presented in Table 2 on page viii. Of the 48 sites reported, 36 are located i n three western states - Colorado (27 sites), Wyoming (5 sites), and Utah (4 sites). Based upon t h e data submitted, the sites were categorized into three broad radiological status categories -- controlled, unstabilized, and risk to the public. At controlled sites, the residue is stabilized, access t o t h e site is controlled, the s i t e is well monitored, and does not currently constitute a risk to the public. At sites in the unstabilized category, a probability exists for the spread of contamination. Sites in the risk category contain residue which represents a long-term risk to the public under present conditions. Of the 48 reported sites,. 9 (approximately 19%) could be classified in the controlled category; 38 (approximately 79%) were in the unstabilized category and

Review of the incineration of 500 tonnes of radio-active residues

International Nuclear Information System (INIS)

Rodier, J.; Seyfried, P.; Charbonneaux, M.

1969-01-01

During its first five years operation, the incinerator at the Marcoule Centre has burnt almost 500 tonnes of radio-active residues. Improvements in some of the details of the process have been made during this period; they concern the nature of the materials involved. The technical and radiological results for the installation are very favorable, and have made it possible to maintain a high charge factor.Although the overall economic results are not advantageous in the case of ungraded solid residues this method represents nevertheless the best available for eliminating oils, solvents, wood and dead animals. It can also be of use furthermore each time that a dilution in the atmosphere can advantageously be used as a method of disposing of certain radio elements such as tritium or carbon 14 in the form of gases or vapours. (author) [fr

The experimental study of residual radioactivity induced in electrostatic deflector

Directory of Open Access Journals (Sweden)

Xu Chong

2017-01-01

Full Text Available As one of the key components of Sector Focusing Cyclotron at the Institute of Modern Physics, Chinese Academy of Sciences, the electrostatic deflector can be activated by primary and secondary particles, because of a mismatch between the actual value and the design value of the emittance and emergence angle. In addition, it will be struck by more particles, since there is a stray magnetic field and outgas from the surface of the electrostatic deflector. The residual radioactivity in the electrostatic deflector has been studied in two aspects: specific activity and residual dose rate, based on the gamma-ray spectrometry and Fluke 451p ionization chamber, respectively. The specific activity of radionuclides in the main components and the dust on the enclosure have been investigated by using gamma-ray spectrometry. The residual dose rate around the electrostatic deflector has been obtained by Fluke 451p ionization chamber. The results of the study show that there is a non-negligible radiological risk to the staff. This result can be provided as guidance for making a maintenance schedule, so that the dose received by staff can be kept as low as reasonably achievable. Based on the results, advice for "hands-on" maintenance and decommissioning of the SFC have been provided.

Conceptual framework and technical basis for clearance of materials with residual radioactivity

International Nuclear Information System (INIS)

Chen, S.Y.

1997-01-01

The primary impediment to the release of materials containing residual radioactivity from a controlled environment is the lack of a suitable framework within which release standards can be developed. Recently, the 'risk-based' approach has been proposed as an appropriate means of setting standards. The term 'clearance' has been introduced by the International Atomic Energy Commission as a regulatory process for releasing radioactive materials posing trivial risks. A 'trivial' risk level has been determined to be on the order of 10[sup -6] to 10[sup -7] annual risk to an exposed individual, and a population risk of no more than 0.1 annually. Under these strict constraints, exposure scenarios may account for processing, disposal, and product end-use of materials. This paper discusses these scenarios and also describes the technical basis for deriving release levels under the suggested risk (or dose) constraints

The radioactive waste management at IAEA laboratories

International Nuclear Information System (INIS)

Deron, S.; Ouvrard, R.; Hartmann, R.; Klose, H.

1992-10-01

The report gives a brief description of the nature of the radioactive wastes generated at the IAEA Laboratories in Seibersdorf, their origin and composition, their management and monitoring. The management of the radioactive waste produced at IAEA Laboratories in Seibersdorf is governed by the Technical Agreements of 1985 between the IAEA and the Austrian Health Ministry. In the period of 1982 to 1991 waste containers of low activity and radiotoxicity generated at laboratories other than the Safeguards Analytical Laboratory (SAL) were transferred to the FZS waste treatment and storage plant: The total activity contained in these drums amounted to < 65 MBq alpha activity; < 1030 MBq beta activity; < 2900 MBq gamma activity. The radioactive waste generated at SAL and transferred to the FZs during the same period included. Uranium contaminated solid burnable waste in 200 1 drums, uranium contaminated solid unburnable waste in 200 1 drums, uranium contaminated liquid unburnable waste in 30 1 bottles, plutonium contaminated solid unburnable waste in 200 1 drums. In the same period SAL received a total of 146 Kg uranium and 812 g plutonium and exported out of Austria, unused residues of samples. The balance, i.e.: uranium 39 kg, plutonium 133 g constitutes the increase of the inventory of reference materials, and unused residues awaiting export, accumulated at SAL and SIL fissile store as a result of SAL operation during this 10 year period. The IAEA reexports all unused residues of samples of radioactive and fissile materials analyzed at his laboratories, so that the amount of radioactive materials ending in the wastes treated and stored at FZS is kept to a minimum. 5 refs, 7 figs, 3 tabs

Release process for non-real property containing residual radioactive material

International Nuclear Information System (INIS)

Ranek, N.L.; Chen, S.Y.; Kamboj, S.; Hensley, J.; Burns, D.; Fleming, R.; Warren, S.; Wallo, A.

1997-01-01

It is DOE's objective to operate its facilities and to conduct its activities so that radiation exposures to members of the public are maintained within acceptable limits and exposures to residual radioactive materials are controlled. To accomplish this, DOE has adopted Order DOE 5400.51 'Radiation Protection of the Public and the Environment', and will be promulgating IO CR Part 834 to codify and clarify the requirements of DOE 5400.5. Under both DOE 5400.5 and 10 CR Part 834, radioactively contaminated DOE property is prohibited from release unless specific actions have been completed prior to the release. This paper outlines a ten-step process that, if followed, will assist DOE Operations and contractor personnel in ensuring that the required actions established by Order DOE 5400.5 and 10 CR Part 834 have been appropriately completed prior to the release for reuse or recycle of non-real property (e.g., office furniture, computers, hand tools, machinery, vehicles and scrap metal). Following the process will assist in ensuring that radiological doses to the public from the released materials will meet applicable regulatory standards and be as low as reasonably achievable (ALARA)

A radiological legacy. Radioactive residues of the Cold War period

International Nuclear Information System (INIS)

Gonzalez, A.J.

1998-01-01

A dominating feature of the historical period known as the Cold War was the large-scale production and testing, of nuclear weapons. These military activities brought with them an unprecedented generation of radioactive substances. A fraction of these 'Cold War residues' ended up in the atmosphere and were dispersed throughout the world. Some remained in relatively isolated states in underground geological environments at the production or test site. Others have contaminated areas at times accessible to humans. Augmenting this picture are other scenes of a Cold War legacy. Large amounts of radioactive waste and byproducts are in storage from the production of weapons material. At some point, they are expected to be converted to peaceful applications or sent for final disposal. Over the past decade, the IAEA has been asked to play a greater role in helping countries address this Cold War legacy. A number of scientific assessments of radiological situations created by the Cold War have been carried out by experts convened by the IAEA - at nuclear test sites, nuclear production facilities, and waste dumping sites. This edition of the IAEA Bulletin highlights these cooperative activities in the context of international developments and concerns

Release procedures and disposal of radioactive residual substances at the Medical University Hanover (MHH)

International Nuclear Information System (INIS)

Scheller, F.; Behrendt, R.; Harke, H.

2005-01-01

The disposal of all radioactive residual packages of the MHH is regulated by the German radiation protection ordinance from 26 th July 2001; shown in appendix III, table 1, column 5: unrestricted release of solid materials and liquids. All radioactive waste packages are collected and handled by the central MHH department for radiation protection. They are sorted for type, nuclide and specific radioactivity. A few packages can directly be released as conventional waste after performing incoming measurements showing very low activity concentrations. Longer living radionuclides with specific activities above the release limits have to be delivered to the national waste disposal. For direct measurements of gamma-emitting radionuclides we use two in-situ-measuring units (ISOCS, Canberra) and a special release unit with 9 plastic scintillators in a fixed geometry (FR-9 PVT, MED Medizintechnik). Fluid beta-emitting radionuclides are measured by taking a fraction and using liquid scintillation counting (LSC). Solid beta-emitting radionuclides activity are calculated. (orig.)

Method to determine the activity concentration and total activity of radioactive waste

International Nuclear Information System (INIS)

Angeles C, A.

2001-02-01

A characteristic system of radioactive waste is described to determine the concentration of radionuclides activity and the total activity of bundles of radioactive waste. The system this integrated by three subsystems: - Elevator of drums. - Electromechanics. - Gamma spectroscopy. In the system it is analyzed waste of issuing gamma specifically, and this designed for materials of relative low density and it analyzes materials of cylindrical recipients

Synthesis and evaluation of radioactive and fluorescent residualizing labels for identifying sites of plasma protein catabolism

International Nuclear Information System (INIS)

Maxwell, J.L.; Baynes, J.W.; Thorpe, S.R.

1986-01-01

Inulin and lactose were each coupled to tyramine by reductive amination with NaBH 3 CN and the tyramine then labeled with 125 I. Dilactitol- 125 I-tyramine (DLT) and inulin- 125 I-tyramine (InTn) were coupled by reductive amination and cyanuric chloride, respectively, to asialofetuin (ASF), fetuin and rat serum albumin (RSA). Attachment of either label had no effect on the circulating half-lives of the proteins. Radioactivity from labeled ASF was recovered in rat liver (> 90%) by 1 h post-injection and remained in liver with half-lives of 2 and 6 days, respectively, for the DLT and InTn labels. Whole body recoveries of radioactivity from DLT- and InTn labels. Whole body recoveries of radioactivity from DLT- and InTn-labeled RSA were 5 and 6.5 days, respectively, again indicating that the larger glycoconjugate label residualized more efficiently in cells following protein degradation. (Lactitol) 2 -N-CH 2 -CH 2 -NH-fluroescein (DLF) was also coupled to ASF by reductive amination and recovered quantitatively in liver at 1 h post-injection. Native ASF was an effective competitor for clearance of DLF-ASF from the circulation. Fluorescent degradation products were retained in liver with a half-life of 1.2 days. Residualizing fluorescent labels should be useful for identification and sorting of cells active in the degradation of plasma proteins

Total synthesis of fully tritiated Leu-enkephalin by enzymatic coupling

Energy Technology Data Exchange (ETDEWEB)

Hellio, F.; Lecocq, G.; Morgat, J.L.; Gueguen, P. (CEA Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service de Biochimie)

1990-09-01

This paper describes the total enzymatic synthesis of Leu-enkephalin (Tyr-Gly-Gly-Phe-Leu) in which all residues were labelled with tritium. Carboxypeptidase Y from Saccharomyces cerevisiae was the coupling enzyme. ({sup 3}H)-Tyr-NH{sub 2}, ({sup 3}H)-Gly-Oet, ({sup 3}H)-Phe-NH{sub 2} and ({sup 3}H)-Leu-NH{sub 2} were prepared with specific radioactivities ranging between 20 and 60 Ci/mmol (740 to 2220 GBq/mmol). Using a microscale procedure, we obtained a fully tritiated hormone having a specific radioactivity equal to 139 Ci/mmol (5143 GBq/mmol), in agreement with the summation of the specific radioactivities of constituting residue. The radioactive hormone had antigenic properties identical to those of native Leu-enkephalin. It also bound to rat brain opiate receptors like the parental hormone. (author).

Evaluation of dose due to the liberation of the radioactive content present in systems of final disposal of radioactive residues

International Nuclear Information System (INIS)

Amado, V.; Lopez, F.

2006-01-01

The disposal systems of radioactive residuals well-known as repositories near to the surface, are used to dispose residuals that can contain high concentrations of radionuclides of period of short semi disintegration, which they would decay at levels radiologically insignificant in some few decades or in some centuries: and acceptably low concentrations of radionuclides of period of long semi disintegration. The dose that would receive the critic group due to these systems it could be increased by cause of discreet events that affect the foreseen retard time, or by the gradual degradation of the barriers. To this last case it contributes the presence of water, because it implies leaching and dissolution that can give place to radionuclide concentrations in the underground water greater to the prospective ones. The dosimetric evaluation is important because it offers useful objective information to decide if a given repository is adjusted to the purposes of its design and it fulfills the regulatory requirements. In this work a simplified evaluation of the dose that would receive the critic group due to the liberation of contained radionuclides in a hypothetical system of final disposition of radioactive residuals is presented. For it, they are considered representative values of the usually contained activities in this type of systems and they are carried out some approaches of the source term. The study is developed in two stages. In the first one, by means of the Radionuclide pollutant scattering pattern in phreatic aquifers (DRAF) it is considered the scattering of the pollutants in the phreatic aquifer, until the discharge point in the course of the nearest surface water. This model, developed originally in the regulatory branch of the National Commission of Argentine Atomic Energy (CNEA); it solves the transport equation of solutes in porous means in three dimensions, by the finite differences method having in account the soil retention and the radioactive

Demonstration of a computer model for residual radioactive material guidelines, RESRAD

International Nuclear Information System (INIS)

Yu, C.; Yuan, Y.C.; Zielen, A.J.; Wallo, A. III

1989-01-01

A computer model was developed to calculate residual radioactive material guidelines for the US Department of Energy (DOE). This model, called RESRAD, can be run on IBM or IBM-compatible microcomputer. Seven potential exposure pathways from contaminated soil are analyzed, including external radiation exposure and internal radiation exposure from inhalation and food digestion. The RESRAD code has been applied to several DOE sites to derive soil cleanup guidelines. The experience gained indicates that a comprehensive set of site-specific hydrogeologic and geochemical input parameters must be used for a realistic pathway analysis. The RESRAD code is a useful tool; it is easy to run and very user-friendly. 6 refs., 12 figs

Comparison of planar, PET and well-counter measurements of total tumor radioactivity in a mouse xenograft model.

Science.gov (United States)

Green, Michael V; Seidel, Jurgen; Williams, Mark R; Wong, Karen J; Ton, Anita; Basuli, Falguni; Choyke, Peter L; Jagoda, Elaine M

2017-10-01

Quantitative small animal radionuclide imaging studies are often carried out with the intention of estimating the total radioactivity content of various tissues such as the radioactivity content of mouse xenograft tumors exposed to putative diagnostic or therapeutic agents. We show that for at least one specific application, positron projection imaging (PPI) and PET yield comparable estimates of absolute total tumor activity and that both of these estimates are highly correlated with direct well-counting of these same tumors. These findings further suggest that in this particular application, PPI is a far more efficient data acquisition and processing methodology than PET. Forty-one athymic mice were implanted with PC3 human prostate cancer cells transfected with prostate-specific membrane antigen (PSMA (+)) and one additional animal (for a total of 42) with a control blank vector (PSMA (-)). All animals were injected with [ 18 F] DCFPyl, a ligand for PSMA, and imaged for total tumor radioactivity with PET and PPI. The tumors were then removed, assayed by well counting for total radioactivity and the values between these methods intercompared. PET, PPI and well-counter estimates of total tumor radioactivity were highly correlated (R 2 >0.98) with regression line slopes near unity (0.95radioactivity can be measured with PET or PPI with an accuracy comparable to well counting if certain experimental and pharmacokinetic conditions are met. In this particular application, PPI is significantly more efficient than PET in making these measurements. Copyright © 2017 Elsevier Inc. All rights reserved.

Volume of baseline data on radioactivity in drinking water, ground water, waste water, sewage sludge, residues and wastes of the annual report 1988 'Environmental radioactivity and radiation exposure'

International Nuclear Information System (INIS)

Abelmann, S.; Buenger, T.; Fusban, H.U.; Ruehle, H.; Viertel, H.; Gans, I.

1991-01-01

This WaBoLu volume is a shortened version of the annual report by the Federal Ministry of the Environment, Nature Protection and Reactor Safety 'Environmental radioactivity and radiation exposure' and gives an overview of the data on radioactivity in drinking water, ground water, waste water, sewage sludge, residues and wastes, compiled for the area of the Federal Republic of Germany in 1988 by the Institute of Water, Soil and Air Hygiene (WaBoLu) of the Federal Health Office. (BBR) With 22 figs., 15 tabs [de

Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (D&D) from restricted use. This would be addressed in the decommissioning plan (E 1281). It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. Fig. 1 shows the logic diagram for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as “candidate for release based on dose.” 1.2 The objective of this guide is to provide a methodology for distinguishing between material that must be carefully isolated to prevent human contact from that that can be recycled or otherwise disposed of. It applies to material in which the radioactivity is dispersed more or less uniformly throughout the volume of the material (termed residual in bulk form) as opposed to surface contaminated objects. 1.3 Surface contaminated objects are materials externally co...

Recovery of Residual LiCl-KCl Eutectic Salts in Radioactive Rare Earth Precipitates

International Nuclear Information System (INIS)

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

2010-01-01

For the pyrochemical process of spent nuclear fuels, recovery of LiCl-KCl eutectic salts is needed to reduce radioactive waste volume and to recycle resource materials. This paper is about recovery of residual LiCl-KCl eutectic salts in radioactive rare earth precipitates (rare earth oxychlorides or oxides) by using a vacuum distillation process. In the vacuum distillation test apparatus, the salts in the rare earth precipitates were vaporized and were separated effectively. The separated salts were deposited in three positions of the vacuum distillation test apparatus or were collected in the filter and it is difficult to recover them. To resolve the problem, a vacuum distillation and condensation system, which is subjected to the force of a temperature gradient at a reduced pressure, was developed. In a preliminary test of the vacuum distillation/condensation recovery system, it was confirmed that it was possible to condense the vaporized salts only in the salt collector and to recover the condensed salts from the salt collector easily

Search for phosphopeptides in the feces of axenic rats fed radioactive ovine casein

International Nuclear Information System (INIS)

Pelissier, J.P.; Dubos, F.; Daburon, F.

1981-01-01

Radioactive ovine casein was obtained by injecting 100 μCi of 14 C-Ser into the jugular vein of an ewe. The milk collected 17 and 24 h after this injection contained 12% of the radioactivity injected in protein form. The seryl residues were specificially labelled. This casein was used as the only protein source fed to axenic rats; 0.30% of the tracer ingested was found in the feces of those rats. Since phosphoserine represented 25% of the total casein seryl residues, the phosphopeptides may not be selectively unabsorbable [fr

Comparison of planar, PET and well-counter measurements of total tumor radioactivity in a mouse xenograft model

International Nuclear Information System (INIS)

Green, Michael V.; Seidel, Jurgen; Williams, Mark R.; Wong, Karen J.; Ton, Anita; Basuli, Falguni; Choyke, Peter L.; Jagoda, Elaine M.

2017-01-01

Introduction: Quantitative small animal radionuclide imaging studies are often carried out with the intention of estimating the total radioactivity content of various tissues such as the radioactivity content of mouse xenograft tumors exposed to putative diagnostic or therapeutic agents. We show that for at least one specific application, positron projection imaging (PPI) and PET yield comparable estimates of absolute total tumor activity and that both of these estimates are highly correlated with direct well-counting of these same tumors. These findings further suggest that in this particular application, PPI is a far more efficient data acquisition and processing methodology than PET. Methods: Forty-one athymic mice were implanted with PC3 human prostate cancer cells transfected with prostate-specific membrane antigen (PSMA (+)) and one additional animal (for a total of 42) with a control blank vector (PSMA (−)). All animals were injected with [ 18 F] DCFPyl, a ligand for PSMA, and imaged for total tumor radioactivity with PET and PPI. The tumors were then removed, assayed by well counting for total radioactivity and the values between these methods intercompared. Results: PET, PPI and well-counter estimates of total tumor radioactivity were highly correlated (R 2 > 0.98) with regression line slopes near unity (0.95 < slope ≤ 1.02) and intercepts near zero (−0.001 MBq ≤ intercept ≤0.004 MBq). Conclusion: Total mouse xenograft tumor radioactivity can be measured with PET or PPI with an accuracy comparable to well counting if certain experimental and pharmacokinetic conditions are met. In this particular application, PPI is significantly more efficient than PET in making these measurements.

Fallout total β radioactivity in every rainfall in Aichi prefecture

International Nuclear Information System (INIS)

Ohnuma, Shoko; Chaya, Kunio; Shimizu, Michihiko; Tomita, Ban-ichi; Hamamura, Norikatsu

1983-01-01

Fallout total β radioactivity was measured in every rainfall in the period from 1962 to 1981. Maximum value of monthly fallout was 462 mCi/km 2 at May 1966. Considering changes of monthly fallout, it was assumed that these 20 years were divided to 3 periods and these changes reflected the history of nuclear explosion tests in the world. Maximum value of annual fallout was 1,154 mCi/km 2 in 1963. Average of annual fallout in 1973 to 1981 was about 1/40 of maximum value. It was confirmed that changes of annual fallout were almost corresponded with changes of annual deposition of 90 Sr and 137 Cs in Tokyo reported by Katsuragi et al. Estimating the staying time of 90 Sr and 137 Cs at Stratosphere by the use of annual fallout of total β radioactivity and annual deposition of these radionuclides, 90 Sr was 1.3 years and 137 Cs was 1.5 years. Also, annual correlation between monthly fallout and monthly rainfall was regarded as significant in only 6 years of these 20 years. (author)

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

International Nuclear Information System (INIS)

1997-06-01

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

Total and occluded residual gas content inside the nuclear fuel pellets

International Nuclear Information System (INIS)

Moura, Sergio C.; Fernandes, Carlos E.; Oliveira, Justine R.; Machado, Joyce F.; Guglielmo, Luisa M.; Bustillos, Oscar V.

2009-01-01

This work describes three techniques available to measure total and occluded residual gases inside the UO 2 nuclear fuel pellets. Hydrogen is the major gas compound inside these pellets, due to sintering fabrication process but Nitrogen is present as well, due to storage atmosphere fuel. The total and occluded residual gas content inside these pellets is a mandatory requirement in a quality control to assure the well function of the pellets inside the nuclear reactor. This work describes the Gas Extractor System coupled with mass spectrometry GES/MS, the Gas Extractor System coupled with gas chromatography GES/GC and the total Hydrogen / Nitrogen H/N analyzer as well. In the GES, occlude gases in the UO 2 pellets is determinate using a high temperature vacuum extraction system, in which the minimum limit of detection is in the range 0.002 cc/g. The qualitative and quantitative determination of the amount of gaseous components employs a mass spectrometry or a gas chromatography technique. The total Hydrogen / Nitrogen analyzer employ a thermal conductivity gas detector linked to a gaseous extractor furnace which has a detection limit is in the range 0.005 cc/g. The specification for the residual gas analyses in the nuclear fuel pellets is 0.03 cc/g, all techniques satisfy the requirement but not the nature of the gases due to reaction with the reactor cladding. The present work details the chemical reaction among Hydrogen / Nitrogen and nuclear reactor cladding. (author)

Radionuclides in Bayer process residues: previous analysis for radiological protection

International Nuclear Information System (INIS)

Cuccia, Valeria; Rocha, Zildete; Oliveira, Arno H. de

2011-01-01

Natural occurring radionuclides are present in many natural resources. Human activities may enhance concentrations of radionuclides and/or enhance potential of exposure to naturally occurring radioactive material (NORM). The industrial residues containing radionuclides have been receiving a considerable global attention, because of the large amounts of NORM containing wastes and the potential long term risks of long-lived radionuclides. Included in this global concern, this work focuses on the characterization of radioactivity in the main residues of Bayer process for alumina production: red mud and sand samples. Usually, the residues of Bayer process are named red mud, in their totality. However, in the industry where the samples were collected, there is an additional residues separation: sand and red mud. The analytical techniques used were gamma spectrometry (HPGe detector) and neutron activation analysis. The concentrations of radionuclides are higher in the red mud than in the sand. These solid residues present activities concentrations enhanced, when compared to bauxite. Further uses for the residues as building material must be more evaluated from the radiological point of view, due to its potential of radiological exposure enhancement, specially caused by radon emission. (author)

Derivation of residual radioactive material guidelines for 13 radionuclides present in Operable Unit IV at Brookhaven National Laboratory, Upton, New York

International Nuclear Information System (INIS)

Faillace, E.; Nimmagadda, M.; Yu, C.

1994-12-01

Residual radioactive material guidelines for 13 radionuclides (americium-241; cobalt-60; cesium-137; europium-152, -154, and -155; plutonium-238, -239, and -240; strontium-90; and uranium-234, -235, and -238) were derived for Operable Unit (OU) IV at Brookhaven National Laboratory. This site has been identified for remedial action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986. Single-nuclide guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of OU IV should not exceed a dose constraint of 30 mrem/yr following remedial action for the current use and plausible future use scenarios or a dose limit of 100 mrem/yr for plausible but less likely future use scenarios. The US Department of Energy (DOE) residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for determining residual radioactive material guidelines. Four potential scenarios were considered; each assumed that, for a period of 1,000 years following remedial action, the site would be used without radiological restrictions. The four scenarios varied with regard to the type of site use, time spent at the site, and sources of food consumed

Radiological impact on the workers, members of the public, and environment from the partial decommissioning of Pakistan Research Reactor-I and its associated radioactive residues.

Science.gov (United States)

Ali, A; Orfi, S D; Manzur, H; Aslam, M

2001-05-01

The Pakistan Research Reactor-I (PARR-I) is a swimming pool type research reactor originally designed and built for a thermal power of 5 MW using High Enriched Uranium (HEU) fuel. In 1990-1991 the reactor was redesigned, partially decommissioned and recommissioned to operate with Low Enriched Uranium (LEU) fuel at a thermal power of 10 MW. An essential requirement, construction and commissioning of a wet spent fuel storage bay and fabrication of an irradiated fuel transfer cask were completed before actual dismantling of the reactor core. During the partial decommissioning operations, radioactive waste generated included 600 m3 low-level liquid radioactive waste and 14 m3 of solid radioactive waste with an average specific activity of 4.52 Bq ml(-1) and 2.22 kBq g(-1), respectively. External radiation doses of the workers were determined using TLD (NG 6,7) and direct reading dosimeters. The maximum individual external radiation dose received by any worker during this practice was 5 mSv, which was 25% of the annual dose limit of 20 mSv. Detection and measurement of internal contamination was carried out using bioassay techniques. During the whole operation, not a single case of internal contamination was detected. The ambient radiation levels around waste seepage pits are periodically monitored using TLD (G-2 cards) and G. M. radiation survey meters. Underground migration of radioactivity is checked by analyzing seepage water samples taken from boreholes that have been dug at different locations in the vicinity of the radioactive residues. The monitoring around disposal sites containing radioactive residues has been continued during the last 9 y and will be continued in the future. So far, no rise in the environmental gamma radiation dose level and migration of underground radionuclides has been found in the vicinity of these disposal sites. Working personal during the decommissioning of PARR-I have been found to be radiologically safe. Adherence to the ALARA

Management of thyroid carcinoma with radioactive 131I

International Nuclear Information System (INIS)

Paryani, Shyam B.; Chobe, Rashmi J.; Scott, Walter; Wells, John; Johnson, Douglas; Kuruvilla, Anand; Schoeppel, Sonja; Deshmukh, Abhijit; Miller, Robert; Dajani, Lorraine; Montgomery, Charles Ted; Puestow, Eric; Purcell, John; Roura, Miguel; Sutton, David; Mallett, Ruth; Peer, Jan

1996-01-01

Purpose: To evaluate the role of radioactive 131 I in the management of patients with well differentiated carcinoma of the thyroid. Methods and Materials: Between 1965 and 1995, a total of 117 patients with well-differentiated carcinoma of the thyroid underwent either lobectomy or thyroidectomy followed by 100-150 mCi of 131 I. Results: With a median follow-up of 8 years, only four patients (3%) developed a recurrence of their disease. The 5-year actuarial survival was 97% with a 10-year survival of 91%. There were no severe side effects noted after 131 I therapy. Conclusions: Radioactive 131 I is a safe and effective procedure for the majority of patients with well-differentiated thyroid carcinoma. We currently recommend that all patients undergo a subtotal or total thyroidectomy followed by 131 I thyroid scanning approximately 4 weeks after surgery. If the thyroid scan shows no residual uptake and all disease is confined to the thyroid, we recommend following patients with annual thyroid scans and serum thyroglobulin levels. If there is any residual uptake detected in the neck or if the tumor extends beyond the thyroid, we recommend routine thyroid ablation of 100-150 mCi of radioactive 131 I

Fallout total. beta. radioactivity in every rainfall in Aichi prefecture

Energy Technology Data Exchange (ETDEWEB)

Ohnuma, Shoko; Chaya, Kunio; Shimizu, Michihiko; Tomita, Ban-ichi; Hamamura, Norikatsu (Aichi Prefectural Inst. of Public Health, Nagoya (Japan))

1983-01-01

Fallout total ..beta.. radioactivity was measured in every rainfall in the period from 1962 to 1981. Maximum value of monthly fallout was 462 mCi/km/sup 2/ at May 1966. Considering changes of monthly fallout, it was assumed that these 20 years were divided to 3 periods and these changes reflected the history of nuclear explosion tests in the world. Maximum value of annual fallout was 1,154 mCi/km/sup 2/ in 1963. Average of annual fallout in 1973 to 1981 was about 1/40 of maximum value. It was confirmed that changes of annual fallout were almost corresponded with changes of annual deposition of /sup 90/Sr and /sup 137/Cs in Tokyo reported by Katsuragi et al. Estimating the staying time of /sup 90/Sr and /sup 137/Cs at Stratosphere by the use of annual fallout of total ..beta.. radioactivity and annual deposition of these radionuclides, /sup 90/Sr was 1.3 years and /sup 137/Cs was 1.5 years. Also, annual correlation between monthly fallout and monthly rainfall was regarded as significant in only 6 years of these 20 years.

Radioimmunological determination of total thyroxine in the serum

Energy Technology Data Exchange (ETDEWEB)

Premachandra, Bhartur

1975-09-04

A radioimmunological method to determine total thyroxine in a serum sample is described. The method is as follows: trichloracetic acid and sodium hydroxide are mixed with the sample; radioactive thyroxine is added to the mixture, which is left to reach equilibrium then placed in contact with a resin sponge consisting of a polyurethane foam with intercommunicating cells containing a strongly basic anion exchange resin; the mixture and the resin sponge are incubated, the initial radioactivity of the mixture and resin sponge combination is measured with an appropriate detection system, then the resin sponge is removed from the mixture, washed and its residual radioactivity measured.

Radioimmunological determination of total thyroxine in the serum

International Nuclear Information System (INIS)

Premachandra, Bhartur.

1975-01-01

A radioimmunological method to determine total thyroxine in a serum sample is described. The method is as follows: trichloracetic acid and sodium hydroxide are mixed with the sample; radioactive thyroxine is added to the mixture, which is left to reach equilibrium then placed in contact with a resin sponge consisting of a polyurethane foam with intercommunicating cells containing a strongly basic anion exchange resin; the mixture and the resin sponge are incubated, the initial radioactivity of the mixture and resin sponge combination is measured with an appropriate detection system, then the resin sponge is removed from the mixture, washed and its residual radioactivity measured [fr

Use of radioactive glucosamine in the perfused rat liver to prepare α1-acid glycoprotein (orosomucoid) with 3H- or 14C-labelled sialic acid and N-acetylglucosamine residues

International Nuclear Information System (INIS)

Aronson, N.N. Jr.

1982-01-01

A method was developed whereby [1- 14 C]glucosamine was used in a perfused rat liver system to prepare over 2 mg of α 1 -acid glycoprotein with highly radioactive sialic acid and glucosamine residues. The liver secreted radioactive α 1 -acid glycoprotein over a 4-6 h period, and this glycoprotein was purified from the perfusate by chromatography on DEAE-cellulose at pH3.6. The sialic acid on the isolated glycoprotein had a specific radioactivity of 3.1 Ci/mol, whereas the glucosamine-specific radioactivity was 4.3 Ci/mole. The latter amino-sugar residues on the isolated protein were only 13-fold less radioactive than the initially added [1- 14 C]glucosamine. Orosomucoid with a specific radioactivity of 31.3 μCi/mg of protein was obtainable by using [6- 3 H]glucosamine. Many other radioactive glycoproteins were found to be secreted into the perfusate by the liver. Thus this experimental system should prove useful for obtaining other serum glycoproteins with highly radioactive sugar moieties. (author)

Long-term management of the existing radioactive wastes and residues at the Niagara Falls Storage Site. Draft Environmental Impact Statement

International Nuclear Information System (INIS)

1984-08-01

The statement assesses and compares several alternatives for long-term management of the existing radioactive wastes and residues at the Niagara Falls Storage Site (NFSS), Lewiston, New York. The alternatives include: (1) no action (continued interim storage at NFSS within a diked and capped containment area), (2) long-term management at NFSS (improved containment, with or without modified form of the residues), (3) long-term management at other DOE sites (Hanford, Washington, or Oak Ridge, Tennessee), and (4) offsite management of the residues at Hanford or Oak Ridge and either leaving the wastes at NFSS or removing them for disposal in the ocean. In addition to alternatives analyzed in depth, several options are also considered, including: other modifications of residue form, modification of the basic conceptual designs, other containment design options, transportation routes, and transportation modes. The radiological health effects (primarily increased risk of cancer) associated with long-term management of the wastes and residues are expected to be smaller than the nonradiological risks of occupational and transportation-related injuries and deaths. During the action period, the risk is highest for workers if all wastes and residues are moved to Hanford. The risk is highest for the general public if the residues are moved to Hanford and the wastes are moved to the ocean. Dispersal of the slightly contaminated wastes in the ocean is not expected to result in any significant impacts on the ocean environment or pose any significant radiological risk to humans. For all alternatives, if controls ceased, there would be eventual dispersion of the radioactive materials to the environment. If it is assumed that all controls cease, predicted time for loss of covers over the buried materials ranges from several hundred years to more than two million years, depending on the use of the land surface

Advantages of the segregation step for the radioactive waste management

International Nuclear Information System (INIS)

Medeiros, Regina Bitelli; Mattos, Maria Fernanda S.S.

2002-01-01

Due to the increasing use of radioactive materials in the research activities, the waste management is essential to guarantee personnel safety and the preservation of the environmental quality. It is possible to determine the date of discharge in the public sewage treatment system based on the estimated activity of the radioactive waste and on the solid waste discharge limit of 74 Bq/g as recommended by the radiation protection rules. The goal of this work is to demonstrate the advantages of the waste segregation by specific activity as a means of minimization of the stored waste. The residual specific activity and volume were estimated in the several steps of assays using 32 P and 3 H. The storage times were calculated and compared with the estimated time considering the residual activity as 2 % of the total activity used in the experiment. The segregation by steps of the assay allowed for the reduction of the waste volume and stored time. In the assays with 3 H only 20 % of the total waste generated was stored and in the assays with 32 P it was possible to discharge 90 % of the radioactive waste after 38 days. (author)

Minimization of zirconium chlorinator residues

International Nuclear Information System (INIS)

Green, G.K.; Harbuck, D.D.

1995-01-01

Zirconium chlorinator residues contain an array of rare earths, scandium, unreacted coke, and radioactive thorium and radium. Because of the radioactivity, the residues must be disposed in special waste containment facilities. As these sites become more congested, and with stricter environmental regulations, disposal of large volumes of wastes may become more difficult. To reduce the mass of disposed material, the US Bureau of Mines (USBM) developed technology to recover rare earths, thorium and radium, and unreacted coke from these residues. This technology employs an HCl leach to solubilize over 99% of the scandium and thorium, and over 90% of the rare earths. The leach liquor is processed through several solvent extraction stages to selectively recover scandium, thorium, and rare earths. The leach residue is further leached with an organic acid to solubilize radium, thus allowing unreacted coke to be recycled to the chlorinator. The thorium and radium waste products, which comprise only 2.1% of the original residue mass, can then be sent to the radioactive waste facility

Surveillance of radioactivity in imported foods marketed in Aichi Prefecture

International Nuclear Information System (INIS)

Ohnuma, Shoko; Kosako, Maki; Tomita, Banichi

2002-01-01

To assess the effects of radioactive contamination by the Chernobyl nuclear plant accident, the authors examined imported foods marketed in Aichi Prefecture from 1988 to 1999 for residual radioactivity. The concentration of both 134 Cs and 137 Cs was determined with an NaI(Tl) detector in 940 samples, including cereals and processed cereals (23%), vegetables and processed vegetables (19%), fruits and processed fruits (17%), including wines (6%), cheese and dairy products (12%), drinking water (11%), confections (6%), and other foods (12%). The countries of origin were Italy (35%), France (2%), Germany (5%), Denmark (4%), the Netherlands (4%), other European Countries (21%), the United States (5%), and other Countries (5%). None of the imported foods tested contained a total residual 134 Cs and 137 Cs radioactivity exceeding 370 Bq/Kg, the preliminary limit set by the government, but 1.3% of the imported foods contained more than 5 Bq/Kg, the lower limit of detection. Both the numbers and rates of imported foods containing radioactivity have clearly been decreasing since the accident, but it was noteworthy that raspberry juice produced in the Netherlands in 1998, 12 years after the accident, contained the highest level of residual radioactivity in this survey (94 Bq/Kg). If it were processed to enriched juice and jam, its radioactivity might exceed the preliminary limit. Since processed and enriched fruits are not currently included among inspected foods, fruits in them whose radioactivity exceeds the limit can be marketed, and thus the present inspection system should be assessed. The preliminary radioactivity limit was determined based on the accident at the Chernobyl nuclear plant, and it will be necessary to set new preliminary limits if a new, unexpected nuclear accident occurs. This surveillance data is expected to served as reference data. (K.H.)

Solid radioactive waste: evaluation of residual activity in nuclear medicine services

International Nuclear Information System (INIS)

Alabarse, Frederico G.; Xavier, Ana M.; Magalhaes, Maisa H.; Guerrero, Jesus S.P.

2009-01-01

An experimental programme to estimate, with a better degree of accuracy, the activity that remains adsorbed in flasks and syringes used in Nuclear Medicine Services for the administration of radionuclides to patients submitted to diagnostic or therapy is been conducted under the coordination of the Radioactive Waste Division of the Brazilian Nuclear Energy Commission, CNEN. The adopted recommendation in Brazil to allow an expedite solid waste management in nuclear medicine facilities, up to the present, is to consider that 2% of the initial activity remains adsorbed in the solid waste, which easily allows the calculation of the storage time to achieve regulatory clearance levels by decay. This research evaluates 17 different kinds of radiopharmaceuticals and three radioisotopes: 99m Tc, 67 Ga and 201 Tl. Results obtained by means of a weighting method to estimate the residual mass in flasks show that the ratio of the mass of the liquid that remains in the solid waste to the mass of the empty flask is constant. This suggests that the residual activity depends on the initial activity concentration of radiopharmaceutical contained in each flask, as assumed by the regulatory body. Additionally, results obtained by determining the remaining activity in flasks, shortly after the injection of its radionuclide contents in patients, indicate that an average value for the residual activity of the order of 10% of the initial activity contained in the flasks or syringes should be adopted to determine the decay storage time before the release of solid waste in the urban conventional land fill disposal system. The 'rule of thumb' of 10 half-lives for storage before clearance is also discussed in the present work. (author)

Residual radioactivity in the soil of the Semipalatinsk Nuclear Test Site in the former USSR.

Science.gov (United States)

Yamamoto, M; Tsukatani, T; Katayama, Y

1996-08-01

This paper deals with our efforts to survey residual radioactivity in the soil sampled at the Semipalatinsk Nuclear Test Site and at off-site areas in Kazakhstan. The soil was sampled at the hypocenter where the first Soviet nuclear explosion was carried out on 29 August 1949, and at the bank of the crater called "Bolapan," which was formed by an underground nuclear detonation on 15 January 1965 along the Shagan River. As a comparison, other soil was also sampled in the cities of Kurchatov and Almaty. These data have allowed a preliminary evaluation of the contemporary radioactive contamination of the land in and around the test site. At the first nuclear explosion site and at Bolapan, higher than background levels of 239,240Pu with weapons-grade plutonium were detected together with fission and activation products such as 137Cs, 60Co, 152Eu, and 154Eu.

Measurement of total body radioactivity in man

International Nuclear Information System (INIS)

Naversten, Y.

1982-01-01

Techniques for the determination of whole-body radioactivity in man using uncollimated NaI(Tl) detectors have been studied. Geometrical effects and photon attenuation effects due to the different shapes of humans as well as due to varying in-vivo radioactivity distributions have been evaluated particularly for scanning-bed geometries and the chair geometry. Theoretically it is shown that the attenuation effects are generally dominating, for full-energy-peak pulse-range methods. For the application in radiation protection a cheap and simple chair-geometry unit has been constructed and used at various places distantly from the home-laboratory, for studies of body activity of Cs-137 in northern Sweden. High body activities were found particularly in reindeer-breeding Lapps. The elimination rate of Cs-137 in man was studied in the stationary whole-body counter in Lund as well as with the field-system. For the study of the performances at low and high photon energies clinical applications of methods for gastro-intestinal absorption of vitamin B12 (Co-57; 122 keV) and total body potassium determination (K-40; 1.46 MeV, K-42; 1.52 MeV) have been evaluated. Theoretical and experimental results as well as experiences of applications in radiation protection and medicine show that the scanning-bed geometry effectively evens out redistributional effects. For optimum results, however, scatter-energy pulse-ranges rather than full-energy-peak ranges should be used. (Auth.)

Management of NORM Residues

International Nuclear Information System (INIS)

2013-06-01

The IAEA attaches great importance to the dissemination of information that can assist Member States in the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the nuclear fuel cycle and nuclear applications, and that address the legacy of past practices and accidents. However, radioactive residues are found not only in nuclear fuel cycle activities, but also in a range of other industrial activities, including: - Mining and milling of metalliferous and non-metallic ores; - Production of non-nuclear fuels, including coal, oil and gas; - Extraction and purification of water (e.g. in the generation of geothermal energy, as drinking and industrial process water; in paper and pulp manufacturing processes); - Production of industrial minerals, including phosphate, clay and building materials; - Use of radionuclides, such as thorium, for properties other than their radioactivity. Naturally occurring radioactive material (NORM) may lead to exposures at some stage of these processes and in the use or reuse of products, residues or wastes. Several IAEA publications address NORM issues with a special focus on some of the more relevant industrial operations. This publication attempts to provide guidance on managing residues arising from different NORM type industries, and on pertinent residue management strategies and technologies, to help Member States gain perspectives on the management of NORM residues

Summary of industrial impacts from recycled radioactive scrap metals

International Nuclear Information System (INIS)

Dehmel, J.-C.; Harrop, J.; MacKinney, J.A.

1995-01-01

During operation, decontamination, and dismantlement, nuclear facilities are generating significant quantities of radioactive scrap metal (RSM). Future decommissioning will generate even more RSM. The petroleum industry also generates RSM in the form of equipment contaminated with naturally occurring radioactivity. Finally, the accidental melting of radioactive sources in steel mills has generated smaller amounts of contaminated metals. Steel mills, smelters, and foundries could recycle these materials, which might then appear in finished products or as feedstocks used by other industries. If introduced in this manner, residual radioactivity can adversely affect the performance of certain products. Such products include computers and other devices that rely on integrated circuits. The most important effect of residual radioactivity on integrated circuits is a phenomenon known as 'single event upsets or soft errors.' Radioactivity can also adversely affect the performance of products such as photographic film and components designed to measure the presence of radioactivity. Radioactivity that raises background count-rates to higher levels could affect the performance of radiation monitoring systems and analytical equipment. Higher background count-rates would lead to reduced sensitivity and lower resolution in spectroscopic systems. The computer, photographic, and radiation measurement industries have taken steps to minimize the impact of residual radioactivity on their products. These steps include monitoring manufacturing processes, specifying material acceptance standards, and screening suppliers. As RSM is recycled, these steps may become more important and more costly. This paper characterizes potentially impacted industries and vulnerability and effects due to the presence of residual radioactivity. Finally, the paper describes practices used to limit the impact of residual radioactivity. (J.P.N.)

Some aspects of the technology improvement for heat reprocessing of the combustible radioactive wastes and ash residue conditioning

International Nuclear Information System (INIS)

Dmitriev, S.A.; Lifanov, F.A.; Knyazev, I.A.; Buravchenko, N.N.; Sobolev, I.A.; Mamaev, L.A.; Alekseev, A.N.; Simagina, O.S.

1991-01-01

The results of studies devoted to increasing the efficiency of thermal reprocessing (combustion) of organic low- and intermediate-level radioactive wastes are given. The new most efficient three-stage process including: 1) gasification and pyrolysis of an organic material with volatile product release, 2) coke residual combustion, ash and noncombustible materials melting, 3) combustion of volatile products of thermal decomposition is developed on the basis of the analysis of solid radioactive waste combustion schemes, mathematical simulation and laboratory studies. Experimental bed, in which these processes are realized, is created. The results obtained in it have allowed one to begin designing of the pilot-commercial plant with shaft furnace having the capacity up to 200 kg/h for solid wastes

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

International Nuclear Information System (INIS)

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

1992-01-01

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

Software application for a total management of a radioactive facility

International Nuclear Information System (INIS)

Mirpuri, E.; Escudero, R.; Macias, M.T.; Perez, J.; Sanchez, A.; Usera, F.

2008-01-01

The use of radiological material and/or equipment that generate ionizing radiation is widely extended in biological research. In every laboratory there are a large variety of methods, operations, techniques, equipment, radioisotopes and users related to the work with ionizing radiation. In order to control the radioactive material, users and the whole facility a large number of documents, databases and information is necessary to be created by the manager of the Radioactivity Facility. This kind of information is characterized by a constant and persistent manipulation and includes information of great importance such as the general management of the radioactive material and waste management, exposed workers vigilance, controlled areas access, laboratory and equipment reservations, radiological inspections, etc. These activities are often complicated by the fact that the main manager of the radioactive facility is also in charge of bio-safety and working prevention issues so the documents to generate and manipulate and the procedures to develop are multiplied. A procedure to access and manage all these files is highly recommended in order to optimize the general management of the facility, avoiding loss of information, automating all the activities and allowing data necessary for control easily accessible. In this work we present a software application for a total management of the facility. This software has been developed by the collaboration of six of the most important research centers from Spain in coordination with the company 'Appize soluciones'. This is a flexible and versatile application that adapts to any specific need of every research center, providing the appropriate reports and checklist that speed up to general management and increase the ease of writing the official documents, including the Operations Book. (author)

Costs related to radioactive residues from nuclear power

International Nuclear Information System (INIS)

1988-06-01

The nuclear power enterprises are responsible for proper actions for safe handling and final storage of spent nuclear fuel and radioactive waste from Swedish nuclear power facilities. The most important actions are to plan, build and operate necessary plants and systems. The nuclear power enterprises have designated Swedish Nuclear Fuel and Waste Management Co., (SKB), to perform these tasks. In this report calculations concerning costs to carry out these tasks are presented. The calculations are based upon a plan prepared by SKB. The plan is described in the report. As final storage of the long lived and highly radioactive waste is planned to take place in the 21st century continuing research and development may indicate new methods which may affect system design as well as costs in a simplifying way. Plants and systems already operational are: Transport systems for radioactive waste products; A central temporary storage for spent nuclear fuel, 'CLAB'; A final storage for radioactive waste from operating nuclear facilities, 'SFR 1'. (L.F.)

Gamma-spectrometric and total alpha-beta counting methods for radioactivity analysis of deuterium depleted water

International Nuclear Information System (INIS)

Ferdes, Ov. S.; Mladin, C.; Vladu, Mihaela; Bulubasa, G.; Bidica, N.

2008-01-01

According to national regulations, as well as to the EU directive on the quality of drinking water, the radionuclide concentrations represent some of the drinking water quality parameters. Among the most important radioactivity content parameters are: the total alpha and total beta concentration (Bq/l); K-40 content, and the gamma-nuclides volume activities. The paper presents the measuring methods for low-level total alpha and/or beta counting of volume samples, as well as the high-resolution gamma-ray spectrometric method used to measure the volume activity of nuclides in drinking water. These methods are applied to monitor the radioactivity content and quality of the QLARIVIA brand of Deuterium depleted water (DDW). There are discussed the performances of these applied methods as well as some preliminary results. (authors)

Phase II, Title I engineering assessment of radioactive sands and residues, Lowman Site, Lowman Idaho

Energy Technology Data Exchange (ETDEWEB)

1977-12-01

An engineering assessment was performed of the problems resulting from the existence of radioactive uranium sand residues at the Lowman, Idaho, site. Services normally include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas release from the 90,000 tons of sand residues at the Lowman site constitutes the most significant environmental impact, although external gamma radiation is also a factor. The two alternative actions presented are dike construction, fencing, and maintenance (Option I); and consolidation of the piles, addition of a 2-ft-thick stabilization cover, and on-site cleanup (Option II). Both options include remedial action at off-site structures. Cost estimates for the two options are $393,000 and $590,000.

Phase II, Title I engineering assessment of radioactive sands and residues, Lowman Site, Lowman Idaho

International Nuclear Information System (INIS)

1977-12-01

An engineering assessment was performed of the problems resulting from the existence of radioactive uranium sand residues at the Lowman, Idaho, site. Services normally include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas release from the 90,000 tons of sand residues at the Lowman site constitutes the most significant environmental impact, although external gamma radiation is also a factor. The two alternative actions presented are dike construction, fencing, and maintenance (Option I); and consolidation of the piles, addition of a 2-ft-thick stabilization cover, and on-site cleanup (Option II). Both options include remedial action at off-site structures. Cost estimates for the two options are $393,000 and $590,000

The tyrosyl residues in creatine kinase. Modification by iodine.

Science.gov (United States)

Fattoum, A; Kassab, R; Pradel, L A

1975-10-20

The effect of the iodination of tyrosyl residues in creatine kinase from rabbit muscle has been investigated at alkaline pH after reversible masking of the reactive thiol groups. The conversion of 4-5 tyrosyl residues to monoiodotyrosines as measured by spectrotitration and by radioactive iodine labelling resulted in almost total loss of enzymic activity. The modified enzyme was unable to bind its nucleotide substrates but no significant conformational change was revealed by optical rotatory dispersion or Stokes radius measurements. However, change in the reactivity of some non-essential thiol groups, presumably those located near the active thiol groups, was observed.

Dose estimation from residual and fallout radioactivity, 1

International Nuclear Information System (INIS)

Takeshita, Kenji

1975-01-01

External dose rates and cumulative doses for early entrants from areal surveys and simulated experiments are reviewed. The average cumulative doses to infinity at the hypocenters were 101 rad in Hiroshima and 32 rad in Nagasaki, with a variation of about 60 percent. Radioactive fallout areas nearly matched the ''black rain'' areas in Nagasaki and in Hiroshima. Radioactivity in the fallout areas was affected by radioactive decay and by the leaching and dissipation by rains. Considering these factors, the cumulative dose to infinity in the fallout area of Hiroshima was estimated to be 13 rad, excluding internal radiation doses from inhaled and ingested radionuclides. Attempts to estimate radiation dose from internally deposited radionuclides are also described. (auth.)

Distribution of radioactive constituents in river waters

International Nuclear Information System (INIS)

Herranz, M.; Elejalde, C.; Legarda, F.; Romero, F.

1994-01-01

For a research project on the distribution and evaluation of natural and artificial radioactive constituents in ecological segments of Biscay (northeast spain), the amounts of nuclides present in the main river waters were measured. Radioactive procedures include i) total alpha and beta indexes with a gas flow detector, dry residues near to 2 and 10 mg/ cm sup 2, respectively and counting periods of 1000 mn, ii) gamma emitters with a low level gamma spectrometer (Ge-HP detector + 8000 channels analyser) using the dry residue from 8 litres and a counting period of 4 days and iii) statistical treatment of data at 95% confidence.In this paper, ten water samples from the nervion river basin are included. Physical and chemical parameters of samples were also determined by standard procedures, because there is a sharp change in the composition of this river in the first part of the course. Radioactive constituents were identified as follows: a sample has a detectable alpha index, all samples contains beta emitters with a high variability, natural nuclides from uranium and thorium families were detected in some cases. A parallel behaviour is found between samples where K-40 and Cs-137 were found. The paper tries at last to find relations among chemical and radioactive constituents by the application of multivariate statistical methods, specially for the case of Cs-137, the only artificial nuclide identified in this work. 1 tab., 2 figs., 5 refs. (author)

ENTRIA 2014. Memorandum on the disposal of high-level radioactive residuals; ENTRIA 2014. Memorandum zur Entsorgung hochradioaktiver Reststoffe

Energy Technology Data Exchange (ETDEWEB)

Roehlig, Klaus-Juergen; Walther, Clemens; Bach, Friedrich-Wilhelm [Niedersaechsische Technische Hochschule, Braunschweig, Clausthal-Zellerfeld, Hannover (Germany); and others

2014-04-30

The memorandum on the disposal of high-level radioactive residuals covers the following issues: description of the problem: a ''wicked problem'', risks and NIMBY, the site selection law, international boundary conditions; disposal strategy and types of facilities: safety and reversibility, long-term surface storage, deep storage; risk and safety; procedural justice and the site selection process; social innovations and the requirement of long-term institutions; conclusion - central stress fields.

Hydrochemistry and radioactivity in the rivers of Biscay (Spain)

International Nuclear Information System (INIS)

Romero, F.; Herranz, M.; Elejalde, C.; Legarda, F.

1995-01-01

For a research project on the evaluations of radioactive constituents in ecological segments of Biscay (Spain), nuclides in water of the main rivers and hydrochemical parameters (pH, conductivity, temperature, percentage of saturation in oxygen and chemical components) were measured. Radioactive data obtained after statistical treatment at 95% confidence level, were as follows; i) Total alpha and beta idexes with a gas flow detector on dry residues not greater than 2 and 10 mg/cm''2, respectively and ii) gamma emitters with a low level spectrometer (Ge-HP detector + 8000 channels analyser) on the dry residue of more than 8 litres and a counting period of 4 days. This paper include 28 samples from the following rivers: Nervion (10), Ibaizabal (5), Cadagua (8), Barbadun, Butron, Oca, Lea and Artibay. On the basis of average values, studied rivers are characterized as follows: Nervion (important amount of Cs. 137 and the greatest beta index), Ibaizabal (high K.40 contents), Cadagua (the biggest alpha index ) and low radionuclides concentrations in the other rivers. Finally, the application of multivariate statistical techniques, mainly cluster analysis, is tried to find out relations between chemical and radioactive constituents. (Author)

Machine for compacting solid residues

International Nuclear Information System (INIS)

Herzog, J.

1981-11-01

Machine for compacting solid residues, particularly bulky radioactive residues, constituted of a horizontally actuated punch and a fixed compression anvil, in which the residues are first compacted horizontally and then vertically. Its salient characteristic is that the punch and the compression anvil have embossments on the compression side and interpenetrating plates in the compression position [fr

Method to determine the activity concentration and total activity of radioactive waste; Metodo para determinar la concentracion de actividad y actividad total de desechos radiactivos

Energy Technology Data Exchange (ETDEWEB)

Angeles C, A

2001-02-15

A characteristic system of radioactive waste is described to determine the concentration of radionuclides activity and the total activity of bundles of radioactive waste. The system this integrated by three subsystems: - Elevator of drums. - Electromechanics. - Gamma spectroscopy. In the system it is analyzed waste of issuing gamma specifically, and this designed for materials of relative low density and it analyzes materials of cylindrical recipients.

Old radioactive waste storage sites

International Nuclear Information System (INIS)

2008-01-01

After a recall of the regulatory context for the management of old sites used for the storage of radioactive wastes with respect with their activity, the concerned products, the disposal or storage type, this document describes AREVA's involvement in the radioactive waste management process in France. Then, for the different kinds of sites (currently operated sites having radioactive waste storage, storage sites for uranium mineral processing residues), it indicates their location and name, their regulatory status and their control authority, the reference documents. It briefly presents the investigation on the long term impact of uranium mineral processing residues on health and environment, evokes some aspects of public information transparency, and presents the activities of an expertise group on old uranium mines. The examples of the sites of Bellezane (uranium mineral processing residues) and COMURHEX Malvesi (assessment of underground and surface water quality at the vicinity of this installation) are given in appendix

A radioactive controversy

International Nuclear Information System (INIS)

Engler, Veronica

2002-01-01

During 2002, the National Congress of Argentina began discussing the 'Agreement between the Republic of Argentina and Australia on cooperation in the peaceful uses of the nuclear energy'. This document has revived the debate regarding development of a national nuclear industry. The debate was spurred by a commercial contract signed in 2000 by INVAP, an Argentinean company who sold a nuclear reactor to the ANSTO, Australian Nuclear and Technology Organization. More than sixty non-governmental organizations are opposed to the ratification of the agreement, because they interpret that the text leaves the door wide open for the transport and deposit of Australian nuclear waste to Argentina, to be processed in national territory. Article 41 of the Argentinean National Constitution, explicitly prohibits the generation of any income from 'radioactive residues'. Those who support the agreement say that it does not promote the deposit of nuclear waste in Argentina, and argue that environmentalists are hampering efforts of this advanced technological industry to flourish in Argentina. The point of conflict in the agreement lies in article 12, which states that Argentina will continue the process of reactor-driven irradiated fuel outside Argentina. Once the treatment is completed, the fuel conditioned and the resulting waste must return to the country of origin for their storage. The possibility of spent fuel being sent to Argentina lies in the hypothetical case that the French company Cogema, which currently holds treatment responsibility, stops treatment sometime within the next fifteen years, when the fuel must be treated. The non-ratification of the agreement on Argentina part will not imply any sort of impediment in the realization of the reactor, it will only put on hold the possibility that the Australians spent fuels will complete treatment in Argentina. The constitutionality of the agreement lies in the question of waste, but this too is not a simple question. The

Radiation doses from residual radioactivity

International Nuclear Information System (INIS)

Okajima, Shunzo; Fujita, Shoichiro; Harley, John H.

1987-01-01

requires knowing the location of the person to within about 200 m from the time of the explosion to a few weeks afterwards. This is an effort that might be comparable to the present shielding study for survivors. The sizes of the four exposed groups are relatively small; however, the number has been estimated only for those exposed to fallout in the Nishiyama district of Nagasaki. Okajima listed the population of Nishiyama as about 600 at the time of the bomb. No figures are available for the other three groups. The individual exposures from residual radiation may not be significant compared with the direct radiation at the time of the bomb. On the other hand, individuals with potential exposure from these sources are dubious candidates for inclusion in a cohort that was presumably not exposed. For comparison with organ doses estimated in other parts of this program, the exposure estimates are converted to absorbed dose in tissue. The first conversion of exposure to absorbed dose in air uses the factor rad in air 0.87 x exposure in R. UNSCEAR uses an average combined factor of 0.7 to convert absorbed dose in air to absorbed dose in tissue for the whole body. This factor accounts for the change in material (air to tissue) and for backscatter and the shielding afforded by other tissues of the body. No allowance for shielding by buildings has been included here. The cumulative fallout exposures given above become absorbed doses in tissue of 12 to 24 rad for Nagasaki and 0.6 to 2 rad for Hiroshima. The cumulative exposures from induced radioactivity become absorbed doses in tissue of 18 to 24 rad for Nagasaki and about 50 rad for Hiroshima. (author)

Development of treatment method for stillage residues of liquid radioactive wastes to remove organic substances and transuranium elements

International Nuclear Information System (INIS)

Rudenko, L.I.; Dzhuzha, O.V.; Khan, V.E.

2008-01-01

The paper presents the results of the study into the laws that govern the process of treating by oxidation the stillage residues of liquid radioactive wastes to remove organic compounds and transuranium elements with the use of hydrogen peroxide, potassium permanganate and subsequent ultra-filtration. The optimum oxidisation regime has been defined on the basis of this study to ensure that the initial dichromate oxidability of LRW's stillage residues decreases from 6,000-9,500 to 500-1,000 mg O/I, whereas the TUE activity associated with the key isotopes is reduced by 74-87 % for 238,239,240 Pu, by 94-95 % for 241 Am, and by 90-95 % for 244 Cm. The concentration of uranium decreases by 94-99 %. It is proposed to implement this method at the Chernobyl NPP site.

Radioactive waste containment

International Nuclear Information System (INIS)

Beranger, J.-C.

1978-01-01

The problem of confining the radioactive wastes produced from the nuclear industry, after the ore concentration stage, is envisaged. These residues being not released into the environment are to be stored. The management policy consists in classifying them in view of adapting to each type of treatment, the suitable conditioning and storage. This classification is made with taking account of the following data: radioactivity (weak, medium or high) nature and lifetime of this radioactivity (transuranians) physical nature and volume. The principles retained are those of volume reduction and shaping into insoluble solids (vitrification) [fr

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

Radioactivity and deep geothermal energy; Radioaktivitaet und tiefe Geothermie

Energy Technology Data Exchange (ETDEWEB)

Janczik, Sebastian; Kaltschmitt, Martin [Technische Univ. Hamburg-Harburg (Germany). Inst. fuer Umwelttechnik und Energiewirtschaft; Merkel, Broder [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Geologie

2012-02-15

Due to recent developments in energy politics renewable energies get more and more importance in Germany. This is especially true for geothermal energy representing a promising option for the environmentally sound and secure generation of heat and electricity. But there are a lot of very emotional discussions due to radioactive residues and wastes produced by a geothermal plant. Thus this paper compares radioactivity resulting from geothermal energy with radioactivity coming from other natural sources. In doing so it becomes obvious that naturally radioactive sources exist in all parts of the ecosphere (i.e. air, water, soil). The paper shows also that the specific activities of radioactive elements from geothermal energy in form of residues and waste emerge from radioactive decay of nuclides and that their radiation is not higher than the radiation of other naturally occurring radioactive elements. (orig.)

Coal combustion ashes: A radioactive Waste?

International Nuclear Information System (INIS)

Michetti, F.P.; Tocci, M.

1992-01-01

The radioactive substances naturally hold in fossil fuels, such as Uranium and Thorium, after the combustion, are subjected to an increase of concentration in the residual combustion products as flying ashes or as firebox ashes. A significant percentage of the waste should be classified as radioactive waste, while the political strategies seems to be setted to declassify it as non-radioactive waste. (Author)

A totally automatic density meter for radioactive solutions

International Nuclear Information System (INIS)

Hochel, R.C.

1987-02-01

A totally automatic density meter for measuring the density of radioactive liquid (plutonium nitrate) samples was developed and built for use at the Savannah River Plant. The measurement cell (vibrating U-tube) and other wetted parts are glovebox-contained and are remoted from the electronics and control instrumentation. The only operator actions required are insertion of a sample vial into the system, starting the analysis, and removing the vial about 90 seconds later. The sample measurement takes about 3 to 4 minutes and uses 10 mL of sample; another 5 to 6 minutes is required for a water/air measurement-control check, which leaves the system ready for the next sample. No water bath is needed because a computer algorithm is applied to the measurement to correct it to a standard reference temperature. The system is normally operated under computer control, but a programmable logic controller is available for backup. The system may also be operated manually by means of a switchpanel. 5 refs., 3 figs

Symposium: Treatment of radioactive residues at Hauptabteilung Dekontaminationsbetriebe (HDB)

International Nuclear Information System (INIS)

Pfeifer, W.

1994-05-01

The twelve seminar papers compiled in the KfK report deal with the current state of the art and the technology available in Germany for the management of radioactive liquid and solid wastes, and radioactive scrap. Some papers discuss particular technical aspects of techniques such as solidification, volume reduction, and compaction. The function of the Waste Collecting Centres of the Laender is explained. (HP) [de

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

International Nuclear Information System (INIS)

Nimmagadda, M.; Yu, C.

1993-04-01

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

Optimization of heat-liberating batches for ash residue stabilization

International Nuclear Information System (INIS)

Karlina, O.K.; Varlackova, G.A.; Ojovan, M.I.; Tivansky, V.M.; Dmitriev, S.A.

1999-01-01

The ash residue obtained after incineration of solid radioactive waste is a dusting poly-dispersed powder like material that contains radioactive nuclides ( 137 Cs, 90 Sr, 239 Pu, hor ( ellipsis)). Specific radioactivity of the ash can be about 10 5 --10 7 Bq/kg. In order to dispose of the ash, residue shall be stabilized by producing a monolith material. The ash residue can be either vitrified or stabilized into a ceramic matrix. For this purpose the ash residue is mixed with fluxing agents followed by melting of obtained composition in the different type melters. As a rule this requires both significant energy consumption and complex melting equipment. A stabilization technology of ash residue was proposed recently by using heat liberating batches-compositions with redox properties. The ash residue is melted due to exothermic chemical reactions in the mixture with heat-liberating batch that occur with considerable release of heat. Stabilization method has three stages: (1) preparation of a mixture of heating batch and ash residue with or without glass forming batch (frit); (2) ignition and combustion of mixed composition; (3) cooling (quenching) of obtained vitreous material. Combustion of mixed composition occurs in the form of propagation of reacting wave. The heat released during exothermic chemical reactions provides melting of ash residue components and production of glass-like phase. The final product consists of a glass like matrix with embedded crystalline inclusions of infusible ash residue components

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.

Radioactive waste solidification material

International Nuclear Information System (INIS)

Nishihara, Yukio; Wakuta, Kuniharu; Ishizaki, Kanjiro; Koyanagi, Naoaki; Sakamoto, Hiroyuki; Uchida, Ikuo.

1992-01-01

The present invention concerns a radioactive waste solidification material containing vermiculite cement used for a vacuum packing type waste processing device, which contains no residue of calcium hydroxide in cement solidification products. No residue of calcium hydroxide means, for example, that peak of Ca(OH) 2 is not recognized in an X ray diffraction device. With such procedures, since calcium sulfoaluminate clinker and Portland cement themselves exhibit water hardening property, and slugs exhibit hydration activity from the early stage, the cement exhibits quick-hardening property, has great extension of long term strength, further, has no shrinking property, less dry- shrinkage, excellent durability, less causing damages such as cracks and peeling as processing products of radioactive wastes, enabling to attain highly safe solidification product. (T.M.)

Development of risk-based computer models for deriving criteria on residual radioactivity and recycling

International Nuclear Information System (INIS)

Chen, S.Y.

1994-01-01

Argonne National Laboratory (ANL) is developing multimedia environmental pathway and health risk computer models to assess radiological risks to human health and to derive cleanup guidelines for environmental restoration, decommissioning, and recycling activities. These models are based on the existing RESRAD code, although each has a separate design and serves different objectives. Two such codes are RESRAD-BUILD and RESRAD-PROBABILISTIC. The RESRAD code was originally developed to implement the US Department of Energy's (DOE's) residual radioactive materials guidelines for contaminated soils. RESRAD has been successfully used by DOE and its contractors to assess health risks and develop cleanup criteria for several sites selected for cleanup or restoration programs. RESRAD-BUILD analyzes human health risks from radioactive releases during decommissioning or rehabilitation of contaminated buildings. Risks to workers are assessed for dismantling activities; risks to the public are assessed for occupancy. RESRAD-BUILD is based on a room compartmental model analyzing the effects on room air quality of contaminant emission and resuspension (as well as radon emanation), the external radiation pathway, and other exposure pathways. RESRAD-PROBABILISTIC, currently under development, is intended to perform uncertainty analysis for RESRAD by using the Monte Carlo approach based on the Latin-Hypercube sampling scheme. The codes being developed at ANL are tailored to meet a specific objective of human health risk assessment and require specific parameter definition and data gathering. The combined capabilities of these codes satisfy various risk assessment requirements in environmental restoration and remediation activities

Development of risk-based computer models for deriving criteria on residual radioactivity and recycling

International Nuclear Information System (INIS)

Chen, Shih-Yew

1995-01-01

Argonne National Laboratory (ANL) is developing multimedia environmental pathway and health risk computer models to assess radiological risks to human health and to derive cleanup guidelines for environmental restoration, decommissioning, and recycling activities. These models are based on the existing RESRAD code, although each has a separate design and serves different objectives. Two such codes are RESRAD-BUILD and RESRAD-PROBABILISTIC. The RESRAD code was originally developed to implement the U.S. Department of Energy's (DOE's) residual radioactive materials guidelines for contaminated soils. RESRAD has been successfully used by DOE and its contractors to assess health risks and develop cleanup criteria for several sites selected for cleanup or restoration programs. RESRAD-BUILD analyzes human health risks from radioactive releases during decommissioning or rehabilitation of contaminated buildings. Risks to workers are assessed for dismantling activities; risks to the public are assessed for occupancy. RESRAD-BUILD is based on a room compartmental model analyzing the effects on room air quality of contaminant emission and resuspension (as well as radon emanation), the external radiation pathway, and other exposure pathways. RESRAD-PROBABILISTIC, currently under development, is intended to perform uncertainty analysis for RESRAD by using the Monte Carlo approach based on the Latin-Hypercube sampling scheme. The codes being developed at ANL are tailored to meet a specific objective of human health risk assessment and require specific parameter definition and data gathering. The combined capabilities of these codes satisfy various risk assessment requirements in environmental restoration and remediation activities. (author)

Instructive for radioactive solid waste management

International Nuclear Information System (INIS)

Mora Rodriguez, Patricia

2014-01-01

An instructive is established for the management system of radioactive solid residues waste of the Universidad de Costa Rica, ensuring the collection, segregation, storage and disposal of waste. The radioactive solid waste have been segregated and transferred according to features and provisions of the Universidad de Costa Rica and CICANUM [es

Recovering method for high level radioactive material

International Nuclear Information System (INIS)

Fukui, Toshiki

1998-01-01

Offgas filters such as of nuclear fuel reprocessing facilities and waste control facilities are burnt, and the burnt ash is melted by heating, and then the molten ashes are brought into contact with a molten metal having a low boiling point to transfer the high level radioactive materials in the molten ash to the molten metal. Then, only the molten metal is evaporated and solidified by drying, and residual high level radioactive materials are recovered. According to this method, the high level radioactive materials in the molten ashes are transferred to the molten metal and separated by the difference of the distribution rate of the molten ash and the molten metal. Subsequently, the molten metal to which the high level radioactive materials are transferred is heated to a temperature higher than the boiling point so that only the molten metal is evaporated and dried to be removed, and residual high level radioactive materials are recovered easily. On the other hand, the molten ash from which the high level radioactive material is removed can be discarded as ordinary industrial wastes as they are. (T.M.)

Fate of leptophos residues in milk products

International Nuclear Information System (INIS)

Zayed, S.M.A.D.; Mohammed, S.I.

1981-01-01

The fate of leptophos residues in various milk products was studied using 14 C-phenyl labelled leptophos. Milk products were prepared from milk fortified with the radioactive insecticide by methods simulating those used in industry. The highest leptophos level was found in butter and the lowest in skim milk and whey. Analysis of the radioactive residues in all products showed the presence of leptophos alone. A trace of the oxon could be detected in whey. The results obtained in this investigation indicated that processing of milk did not affect the nature of leptophos to any appreciable extent. (author)

Therapeutic result of radioactive nuclide 90Sr/90Y treatment in patients with benign prostatic hypertrophy (BPH)

International Nuclear Information System (INIS)

Chen Hanchao; Li Yuying

2008-01-01

Objective: To study the effect of radioactive nuclide 90 Sr/ 90 Y treatment in patients with benign prostatic hypertrophy (BPH). Methods: Sixty patients with BPH were treated with a course of transurethral radioactive nuclide 90 Sr/ 90 Y therapy. Results: The severity of BPH was assessed with four parameters: maximal flow rate (MFR), volume of residual urine (VRU), international prostatic symptom score (IPSS) and volume (size) of prostate. In this series, the total effective rate was 93.33% with no treatment- related mortality. Favorable changes of the parameters after a course of radioactive nuclide therapy were significant. Conclusion: Radioactive nuclide 90 Sr/ 90 Y therapy for patients with BPH was safe, easily performed and quite effective. This procedure is worth popularizing in appropriate patients. (authors)

Radioactive-site-remediation technologies seminar. Speaker slide copies

International Nuclear Information System (INIS)

1992-06-01

The contents of this report include the following: approaches to sampling radioactive heterogeneous waste; soil characterization methodology for determining application of soil washing; vorce (volume reduction/chemical extraction) program; treatment of radioactive compounds in water; polymer solidification of low-level radioactive, hazardous, and mixed waste; in situ vitrification of soils contaminated with radioactive and mixed wastes; decontamination of contaminated buildings; incineration of radioactive waste; in situ stabilization/solidification with cement-based grouts; environmental restoration and waste management; removal of contaminants from soils by electrokinetics; and treatment, compaction, and disposal of residual radioactive waste

Presence of radioactivity in a sewage system: a proposal for radioactivity control

International Nuclear Information System (INIS)

Serradell, Vicente; Ballesteros, Luisa; Ortiz, Josefina

2008-01-01

Most hospitals use radioisotopes in diagnostics and to a lesser extent in therapy. The liquid residues thus generated are usually subjected to treatment before being discharged into the sewage system. Nevertheless, a certain amount of these residues escape from the treatment system and are poured directly into the sewer. In addition, other radioactive products used for research and industrial purposes may also be disposed of in the same way. The waste waters in many sewage systems can therefore be expected to be radiologically contaminated and the need for at least a basic control system in such situations seems obvious. When designing a procedure to measure radioactivity, certain conditions should be borne in mind: 1) The control program has to be simple and inexpensive; 2) Samples must be taken from the appropriate places; 3) Short life radionuclides will probably be present in significant amounts, so that specific recipes should be prepared; 4) Iodine is also frequently present. Special precautions should be taken to keep it in solution. In recent years, the Environmental Radioactivity Laboratory of the Universidad Politecnica de Valencia (Spain) has carried out a series of tests on the Valencia city sewage system and sewage treatment plant in order to design a permanent program to control radioactive contamination of the city's sewage system. This paper presents a proposal which we believe can provide the answer to this problem. (author)

Radioactive residues. Current and prospective problems. Les residus radioactifs. Problems actuels et perspectives

Energy Technology Data Exchange (ETDEWEB)

Gauvenet, A.

1975-07-01

After having described the principal characteristics of radioactive residues, the author examined the current problems posed by liquid and gaseous effluents and stressed that nuclear installations are definitely much less polluting, with an identical power output, than conventional power stations. Research programs have been undertaken in the face of the predictable increase in activity. The gist of the matter is to maintain the absorbed doses at their present level and to study the problem of compounds with a long lifetime, the accumulation of which would create considerable danger on a world scale. With respect to the stockpiling of wastes, the author described the various techniques currently used and cited studies in progress, some of which--such as vitrification--have already come into the first stages of application. After having noted that the waste problem undoubtedly constitutes a technical difficulty and perhaps even more so on the psychological plane, the author defined in conclusion the conditions that should be established so that this problem does not hinder the short- and long-term development of nuclear energy.

Immobilization of acid digestion residue

International Nuclear Information System (INIS)

Greenhalgh, W.O.; Allen, C.R.

1983-01-01

Acid digestion treatment of nuclear waste is similar to incineration processes and results in the bulk of the waste being reduced in volume and weight to some residual solids termed residue. The residue is composed of various dispersible solid materials and typically contains the resultant radioactivity from the waste. This report describes the immobilization of the residue in portland cement, borosilicate glass, and some other waste forms. Diagrams showing the cement and glass virtification parameters are included in the report as well as process steps and candidate waste product forms. Cement immobilization is simplest and probably least expensive; glass vitrification exhibits the best overall volume reduction ratio

Radioactivity of combustion residues from coal-fired power stations

International Nuclear Information System (INIS)

Vom Berg, W.; Puch, K.H.

1996-01-01

Each year in Germany, about 18 mill. t of combustion residues are produced from the combustion of bituminous coal and lignite. They are utilized to a great extent in the construction industry and in mining. During the combustion of coal, the radio-nuclides remain predominantly in the ash. The radionuclide concentration in lignite ash is within the range of that in natural soil. The combustion residues of bituminous coal contain radio-nuclides of a similar order of magnitude as also can occur in natural rock. The utilization of combustion residues in construction materials makes a negligible contribution to radiation exposure through retention in buildings. (orig.) [de

Total effects of contact and residual exposure of bifenthrin and λ-cyhalothrin on the predatory mite Galendromus occidentalis (Acari: Phytoseiidae).

Science.gov (United States)

Hamby, Kelly A; Alifano, Jesse A; Zalom, Frank G

2013-10-01

Pyrethroid insecticides are generally regarded as acutely toxic to predatory phytoseiid mites; however, persistence of hull split spray pyrethroid residues on almond trees and their effects on phytoseiids have not been quantified over time. Hull split, the separation of the almond hull along the suture, exposes the new crop nuts to infestation by Amyelois transitella (Walker) larvae, and is the preferred timing for insecticides applied for their control. Galendromus occidentalis (Nesbitt) is the most important phytoseiid biocontrol agent for web-spinning spider mites in California (USA) almond orchards, and the impact of bifenthrin and λ-cyhalothrin pyrethroid residue on their survival, fertility, and fecundity was determined. The total effects of direct contact with esfenvalerate, permethrin, bifenthrin and λ-cyhalothrin were also evaluated for comparison. The total effects (E) of direct contact treatments of the four pyrethroids ranged from 77.8 % for esfenvalerate to 98.8 % for bifenthrin. Both bifenthrin and λ-cyhalothrin twig residue would be considered harmful (IOBC class 4) following field application at hull split timing. Bifenthrin twig residue would be considered slightly harmful (IOBC class 2) for up to 3.5 months and harmless (IOBC class 1) after 6 months. λ-cyhalothrin residue would be considered moderately harmful (IOBC class 3) for up to 3.5 months following application and harmless (IOBC class 1) after 6 months. Bifenthrin and λ-cyhalothrin twig residue on treated trees significantly reduced G. occidentalis female survival for up to 6 months post-treatment, however total effects (E) classify these residues as harmless (IOBC class 1) after 6 months. Harmful effects of direct and residual exposure following application have implications for the use of these pyrethroids in an integrated mite management program for perennial crops.

Research on atmospheric radioactivity. [In French

Energy Technology Data Exchange (ETDEWEB)

Garrigue, H

1954-01-01

In flight at 2800 m, traces of radioactive particles were gathered, by means of a corona effect similar to that of Sella, and of long period, on April 24, 1954. At Puy-de-Dome (1465 m) after a fall of rain and snow on May 3 to 4, 1954, samples of the fallen residue showed very feeble radioactivity of period 10 days or more. This radioactivity of the airborne particles was independent of their probable natural electrical charge and mobility and was indicative of an atomic cloud.

Natural Gamma Emitters after a Selective Chemical Separation of a TENORM residue: Preliminary Results

International Nuclear Information System (INIS)

Alves de Freitas, Antonio; Abrao, Alcidio; Godoy dos Santos, Adir Janete; Pecequilo, Brigitte Roxana Soreanu

2008-01-01

An analytical procedure was established in order to obtain selective fractions containing radium isotopes ( 228 Ra), thorium ( 232 Th), and rare earths from RETOTER (REsiduo de TOrio e TErras Raras), a solid residue rich in rare earth elements, thorium isotopes and small amount of natural uranium generated from the operation of a thorium pilot plant for purification and production of pure thorium nitrate at IPEN -CNEN/SP. The paper presents preliminary results of 228 Ra, 226 Ra, 238 U, 210 Pb, and 40 K concentrations in the selective fractions and total residue determined by high-resolution gamma spectroscopy, considering radioactive equilibrium of the samples

Radioactivity at the summit of Puy de Dome. [In French

Energy Technology Data Exchange (ETDEWEB)

Garrigue, H

1951-01-01

The radioactivity of the atmosphere was studied systematically by counting the disintegrations of the residue obtained by evaporating melted snow. Three separate radioactivity measurements in the atmosphere apparently reached a max. sometime in 1946.

Residual radioactivity in the soil of the Semipalatinsk Nuclear Test Site in the former USSR

International Nuclear Information System (INIS)

Yamamoto, Masayoshi; Tsukatani, Tsuneo; Katayama, Yukio

1996-01-01

This paper deals with our efforts to survey residual readioactivity in the soil sampled at teh Semipalatinsk Nuclear Test Site and at off-site areas in Kazakhstan. The soil sampled at the hypocenter where the first Soviet nuclear explosion was carried out on 29 August 1949, and at the bank of the crater called open-quotes Bolapan,close quotes which was formed by an underground nuclear detonation on 15 January 1965 along the Shagan River. As a comparison, other soil was also sampled in the cities of Kurchatov and Almaty. These data have allowed a preliminary evaluation of the contemporary radioactive contamination of the land in and around the test site. At the first nuclear explosion site and at Bolapan, higher than background levels of 239,240 Pu with weapons-grade plutonium were detected together with fission and activation products such as 137 Cs, 60 Co, 152 Eu, and 154 Eu. 20 refs., 3 figs., 5 tabs

Standard guide for radioactive pathway methodology for release of sites following decommissioning

International Nuclear Information System (INIS)

Anon.

1989-01-01

The purpose of this guide is to provide guidance in determining site-specific conversion factors for translating between dose limits and residual radioactive contamination levels on equipment structures, and land areas. This guide is to serve as a guide to acceptable methodology for translating the yet to be determined dose limits into allowable levels of residual radioactive materials that can be left at a site following decommissioning

JUSTIFICATION FOR THE RADIOLOGICAL CRITERIA FOR THE USE OF AREAS WITH RESIDUAL RADIOACTIVE CONTAMINATION BASED ON THE DOSE APPROACH

Directory of Open Access Journals (Sweden)

V. Yu. Golikov

2017-01-01

Full Text Available The article presents a methodology for assessing the radiological criteria for the use of the territory (a land plot with buildings with residual radioactive contamination from the so-called “green area”, i.e., complete release from radiation control until a number of restrictions are imposed on the use of the territory. In accordance with the further use of the territory, a range of scenarios and pathways for the exposure of the population was considered. A set of models and their parameters, corresponding to the number of the considered pathways of exposure, was defined. Assuming a uniform distribution of a radionuclide with a unit concentration in the source zone, the distribution of effective doses for the population living in the territory with the residual radioactive contamination for different irradiation scenarios was calculated by stochastic modeling, 95% of the quantile of which was attributed to the dose in the representatives of the critical population group. Next, the value of radiological criteria, depending on the implemented scenario, was determined as the ratio of the dose constraint EL = 0,3 mSv/yr and 95% quantile in the distribution of the effective dose from a unit contamination. The numerical values of radiological criteria for the presence of radionuclides in the soil are presented, both for the radiation scenarios that correspond to the permanent residence of the population in the contaminated territory and for recreational use. A further consideration is given to the so-called worker scenario, which corresponds to the limited time spent on the contaminated territory and the simultaneous effects of radionuclides contained both in the soil and in the construction of the buildings. A comparison of the results of the own calculations with the data of other authors was carried out.

Decree of the 23-rd of June 2015 related to installations implementing radioactive materials, radioactive wastes or solid residues of uranium, thorium or radium ore submitted to authorization according to entry 1716, to entry 1735 and to entry 2797 of the nomenclature of classified installations

International Nuclear Information System (INIS)

Blanc, P.

2015-01-01

This decree defines general prescriptions applicable to installations implementing radioactive materials, to installations used as depository, warehousing or storage of radioactive materials under the form of solid residues of radium, thorium or uranium ore, as well as some processing products, and to installations used for the management of radioactive wastes in an industrial or commercial facility. The decree contains general arrangements about authorisation request, financial guarantees and conditions of exploitation. It addresses measures and arrangements for the management of installations, for the management of radioactive materials and wastes, for the prevention of atmospheric pollution, for the protection of water resources and aquatic media. It also contains general rules for waste management, specific rules for radioactive waste management. It addresses measures and arrangements regarding the prevention of technological risks, the monitoring of installations and of their impact. An appendix addresses the various aspects of the quality management system: organisation and personnel, risk identification and assessment, process management and exploitation monitoring, management of modifications, planning of emergency situation, return on experience, performance monitoring. A last appendix addresses the monitoring of underground waters

Radioactive residues at nuclear sites in the United States of America

International Nuclear Information System (INIS)

Fiore, J.; Rampertaap, A.; Greeves, J.; MacKinney, J.; Raguso, M.; Selstrom, J.

2000-01-01

The United States of America has a large number of sites where radioactive materials have been mined, processed, produced, or used. Upon completion of activities at these sites, some will be cleaned up completely and released for unrestricted future use. However, at other sites, contamination will remain on the site following cleanup, requiring long term institutional controls. Depending on the purpose or the activity conducted at a specific site, these locations are generally under the jurisdiction of a federal agency: the United States Department of Energy, the United States Nuclear Regulatory Commission, the United States Environmental Protection Agency, or the United States Department of Defense. However, under certain conditions, the Nuclear Regulatory Commission relinquishes regulatory authority to individual states to regulate the commercial uses of radioactive materials (except for nuclear reactors), so some locations with radioactive materials are under the jurisdiction of individual states. Other sites with naturally occurring radioactive contamination may also be controlled by individual states. One or two sites under the jurisdiction of each agency are discussed where radioactive materials either existed in the past or exist today, and the source of contamination, the anticipated end state, and the process by which the responsible agency did or will conduct cleanup and site closure are described. Several issues are reviewed that must be addressed in order to design and implement remediations that will ensure long term protection for the environment and future inhabitants. The role of citizens in environmental cleanups is examined, and how institutional controls may be applied to ensure long term protection of remediations that leave some contaminants in place. (author)

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

International Nuclear Information System (INIS)

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

1975-01-01

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

Fate of 14C-allylalcohol herbicide in soils and crop residues

International Nuclear Information System (INIS)

Scheunert, I.; Vockel, D.; Klein, W.; Korte, F.

1981-01-01

Residue disappearance and leaching of 14 C-allylalcohol from different soils were studied in laboratory experiments. Additionally, the uptake of residues by lettuce and carrots was investigated in the greenhouse. In laboratory experiments, residue disappearance and leaching from soils was correlated negatively to the organic matter content. In greenhouse experiments with a sandy loam soil at an application rate normally used in practice, an average of 12.5% of the applied radioactivity was recovered after an eight day interval between application and sowing. Furthermore, an average of 8% (sum in soil and plants) of the applied radioactivity was recovered after lettuce or carrot growing. Uptake of residues was higher by carrots than by lettuce, and higher by lettuce roots than by lettuce tops. No bioaccumulation was observed. The residues in soils and plants were, to a high percent-age, unextractable and, to a smaller extent, fully water-soluble products. Unchanged allylalcohol could not be detected by the analytical methods used

Distribution of natural occurring radionuclide in some industral residues used in new type wall materials

International Nuclear Information System (INIS)

Chen Yingmin; Li Fusheng; Xu Jiaang; Deng Daping; Yuan Ming; Ma Shi; Chen Yue

2006-01-01

Objective: To study the natural radioactive nuclide distribution characteristic of fly ash, gangue and various kinds of slag used in the new-type wall material and offer scientific basis for reducing the radiation dosage that the public suffers. Methods: The activity concentrations of the contents of natural radioactive nuclides of different industral waste residues have been determined by HPGe gamma-ray spectrometry. Results: The mean Raeq is successively fly ash (279.13 Bq kg -1 ), slag (225.69 Bq kg -1 ), gangue (141.26 Bq kg -1 ) from high to low and all of the samples is lower than the limit set in the OECD. The arithmetic mean activities of 236 Ra, 232 Th, 40 K in fly-ash samples are 127.88, 93.83, 221.75 Bq kg -1 ; for coal slag samples are 73.89, 97.13, 283.44 Bq kg -1 and for coal gangue samples are 47.85, 45.21, 413.56 Bq kg -1 . For the same power plant, the radioactive nuclide activity of the fly ash gathered in different time may have very great differences, the maximum can reach more than 2 times of the minimum. Conclusion: the fly ash and slag should be controlled strictly on rational proportion, which should not exceed 70% of the total mass. The mixing of the average radioactive level of the gangue is nearly equal that of to clay, it can be unrestricted in the mixing proportion in process of production. The manufacturer of new-type wall materials should often measure the radioactive level of the industrial waste residue in production. Make the content of radioactive nuclide in the products reach the rational level as low as possible. (authors)

The state of the art on the radioactive metal waste recycling technologies

International Nuclear Information System (INIS)

Oh, Won Jin; Moon, Jei Kwon; Jung, Chong Hun; Park, Sang Yoon

1997-09-01

As the best strategy to manage the radioactive metal wastes which are generated during operation and decommissioning of nuclear facilities, the following recycling technologies are investigated. 1. decontamination technologies for radioactive metal waste recycling 2. decontamination waste treatment technologies. 3. residual radioactivity evaluation technologies. (author). 260 refs., 26 tabs., 31 figs

Method of reducing the volume of radioactive waste

International Nuclear Information System (INIS)

Buckley, L.P.; Burrill, K.A.; Desjardins, C.D.; Salter, R.S.

1984-01-01

There is provided a method of reducing the volume of radioactive waste, comprising: pyrolyzing the radioactive waste in the interior of a vessel, while passing superheated steam through the vessel at a temperature in the range 500 to 700 degrees C, a pressure in the range 1.0 to 3.5 MPa, and at a flow rate in the range 4 to 50 mL/s/m 3 of the volume of the vessel interior, to cause pyrohydrolysis of the waste and to remove carbon-containing components of the pyrolyzed waste from the vessel as gaseous oxides, leaving an ash residue in the vessel. Entrained particles present with the gaseous oxides are filtered and acidic vapours present with the gaseous oxides are removed by solid sorbent. Steam and any organic substances present with the gaseous oxides are condensed and the ash is removed from the vessel. The radioactive waste may be deposited upon an upper screen in the vessel, so that a substantial portion of the pyrolysis of the radioactive waste takes place while the radioactive waste is on the upper screen, and pyrolyzed waste falls through the upper screen onto a lower screen, where another substantial portion of the pyrohydrolysis takes place. The ash residue falls through the lower screen

Identification of a highly reactive threonine residue at the active site of γ-glutamyl transpeptidase

International Nuclear Information System (INIS)

Stole, E.; Seddon, A.P.; Wellner, D.; Meister, A.

1990-01-01

γ-Glutamyl transpeptidase an enzyme of major importance in glutathione metabolism, was inactivated by treating it with L-(αS,5S)-α-amino-3-chloro-4,5-dihydro-5-[3- 14 C]isoxazoleacetic acid. This selective reagent binds stoichiometrically to the enzyme; more than 90% of the label was bound to its light subunit. Enzymatic digestion of the light subunit gave a 14 C-labeled peptide that corresponds to amino acid residues 517-527 of the enzyme and two incomplete digestion products that contain this labeled peptide moiety. The radioactivity associated with this peptide was released with threonine-523 during sequencing by the automated gas-phase Edman method. The light subunit contains 14 other threonine residues and a total of 19 serine residues; these were not labeled. Threonine-523 is situated in the enzyme in an environment that greatly increases its reactivity, indicating that other amino acid residues of the enzyme must also participate in the active-site chemistry of the enzyme

Final disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Kroebel, R [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Wiederaufarbeitung und Abfallbehandlung; Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Abt. zur Behandlung Radioaktiver Abfaelle

1978-08-01

This paper discusses the final disposal possibilities for radioactive wastes in the Federal Republic of Germany and the related questions of waste conditioning, storage methods and safety. The programs in progress in neighbouring CEC countries and in the USA are also mentioned briefly. The autors conclude that the existing final disposal possibilities are sufficiently well known and safe, but that they could be improved still further by future development work. The residual hazard potential of radioactive wastes from fuel reprocessing after about 1000 years of storage is lower that of known inorganic core deposits.

FAO/IAEA model protocol for the determination of bound residues in soil

International Nuclear Information System (INIS)

1986-01-01

A protocol for determining bound pesticide residue content in soils was developed and collaboratively tested by 11 members of the FAO/IAEA Research Co-ordination Committee. The method assumes prior incubation of soil with a radioactive pesticide or related organic compound. The major process steps of the protocol include: (a) Soxhlet extraction of air-dry soil with methanol for 24 h; (b) determination of radioactivity in unextracted soil, in methanol-extracted soil (yielding bound residue content), and in the methanol extract (yielding extractable residue content); and (c) use of triplicate samples per analysis. The participants received lysimeter soils treated six to seven years earlier with 14 C-allyl alcohol (Soil A) or 14 C-hexachloro-benzene (Soil H). The inter-laboratory results first indicated non-homogeneity of Soil A sub-samples, since the initial and bound radioactivity for four laboratories was about half of that found by the remaining seven laboratories. Intra-laboratory (in one laboratory) analyses of sub-subsamples from six 'high-group' laboratories, two 'low-group' laboratories and two additional laboratories confirmed the homogeneity of Soil A and implicated error in the combustion methods at 'low-group' laboratories. The intra- and inter-laboratory coefficients of variation for initial 14 C-content were 4.7% and 7.0%, respectively. Of the residual 14 C in Soil A, 95% was bound; in contrast, only 15% of 14 C in Soil H was bound. The coefficients of variation among ten laboratories, for Soil H, were 8.4% and 18.1% for percentage extractable residue and percentage bound residue, respectively. Some limited testing of alternative protocols, using other solvents or batch extraction, confirmed that the IAEA protocol was most efficient in the extraction of non-bound radioactivity; pre-wetting Soil A may, however, improve extraction. (author)

Classification of solid wastes as non-radioactive wastes

International Nuclear Information System (INIS)

Suzuki, Masahiro; Tomioka, Hideo; Kamike, Kozo; Komatu, Junji

1995-01-01

The radioactive wastes generally include nuclear fuels, materials contaminated with radioactive contaminants or neutron activation to be discarded. The solid wastes arising from the radiation control area in nuclear facilities are used to treat and stored as radioactive solid wastes at the operation of nuclear facilities in Japan. However, these wastes include many non-radioactive wastes. Especially, a large amount of wastes is expected to generate at the decommissioning of nuclear facilities in the near future. It is important to classify these wastes into non-radioactive and radioactive wastes. The exemption or recycling criteria of radioactive solid wastes is under discussion and not decided yet in Japan. Under these circumstances, the Nuclear Safety Committee recently decided the concept on the category of non-radioactive waste for the wastes arising from decommissioning of nuclear facilities. The concept is based on the separation and removal of the radioactively contaminated parts from radioactive solid wastes. The residual parts of these solid wastes will be treated as non-radioactive waste if no significant difference in radioactivity between the similar natural materials and materials removed the radioactive contaminants. The paper describes the procedures of classification of solid wastes as non-radioactive wastes. (author)

Method of treatment of radioactive silts and soils

International Nuclear Information System (INIS)

Varlakov, A.P.; Sobolev, I.A.; Barinov, A.S.; Dmitriev, S.A.; Karlin, S.V.; Flit, V.U.

1997-01-01

To solve the problem of silts and soils that are contaminated with radioactive and toxic substances, the following method has been developed at SIA RADON. The material is mixed with limestone and other components, including up to 70% (mass) of dried residue of liquid radioactive waste. The mixture is heated at 800 to 1,000 C, shredded, and used to form cement. This cementation process may be used to treat radioactive or other chemical waste. The work demonstrated that in the case of silts, for example, the product volume is reduced by a factor of 1.5 to 3 compared to the initial silts volume. A fast hardening, durable product is obtained, the quality of which is not inferior to that obtained by using the traditional binders. For some parameters, e.g., hardening rate and macroelement leaching, the current method is significantly better than the traditional cementation process. It has also been demonstrated that, over a wide range of parameters, when dry residue of liquid radioactive waste is used in the initial mixture, the part of NO x can be reduced to nitrogen, thereby reducing NO x emissions

Nuclear fuel cycle waste recycling technology deverlopment - Radioactive metal waste recycling technology development

International Nuclear Information System (INIS)

Oh, Won Zin; Moon, Jei Kwon; Jung, Chong Hun; Park, Sang Yoon

1998-08-01

With relation to recycling of the radioactive metal wastes which are generated during operation and decommissioning of nuclear facilities, the following were described in this report. 1. Analysis of the state of the art on the radioactive metal waste recycling technologies. 2. Economical assessment on the radioactive metal waste recycling. 3. Process development for radioactive metal waste recycling, A. Decontamination technologies for radioactive metal waste recycling. B. Decontamination waste treatment technologies, C. Residual radioactivity evaluation technologies. (author). 238 refs., 60 tabs., 79 figs

Accumulation of {sup 14}C-trinitrotoluene and related nonextractable (bound) residues in Eisenia fetida

Energy Technology Data Exchange (ETDEWEB)

Belden, Jason B., E-mail: jbelden@okstate.edu [Department of Zoology, Oklahoma State University, Stillwater, OK 74078 (United States); Lotufo, Guillerme R. [US Army Engineer Research and Development Center, Vicksburg, MS 39180 (United States); Chambliss, C. Kevin [Department of Chemistry, Baylor University, Waco, TX 76798 (United States); Fisher, Jonathan C. [Department of Zoology, Oklahoma State University, Stillwater, OK 74078 (United States); Johnson, Dave R.; Boyd, Robert E.; Sims, Jerre G. [US Army Engineer Research and Development Center, Vicksburg, MS 39180 (United States)

2011-05-15

To determine if trinitrotoluene (TNT) forms nonextractable residues in earthworms and to measure the relative degree of accumulation as compared to TNT and its deaminated metabolites, Eisenia fetida was exposed to {sup 14}C-TNT using dermal contact to filter paper or exposure to soil. Nonextractable residues made up 32-68% of total body burden depending on exposure media and depuration time. Parent TNT accounted for less than 3% of radioactivity, while ADNTs accounted for 7-38%. Elimination half-lives were 61-120 h for TNT, ADNTs, and DANTs, which was significantly lower than the half-lives found for nonextractable residues, 201-240 h. However, over 80% of the nonextractable residue was solubilized using weak acid (pH 2). Based on our findings that TNT accumulation occurs primarily as nonextractable residues, which have a longer half-life, and that nonextractable residues can be solubilized, we propose that nonextractable residues could be used as a selective biomarker for assessing TNT contamination. - Highlights: > Trinitrotoluene accumulation in earthworms primarily occurs as nonextractable residues. > Nonextractable residues have a significantly longer half life in the worm as compared to TNT and its solvent-extractable deaminated metabolites. > Nonextractable residue may be useful as a biomarker for exposure to TNT. - The majority of trinitrotoluene accumulation in earthworms occurs as nonextractable residues that have a significantly longer half life in the worm as compared to TNT and its solvent-extractable deaminated metabolites.

Method of solidifying radioactive waste

International Nuclear Information System (INIS)

Hasegawa, Akira; Mihara, Shigeru; Yamashita, Koji; Sauda, Kenzo.

1988-01-01

Purpose: To obtain satisfactory plastic solidification products rapidly and more conveniently from radioactive wastes. Method: liquid wastes contain, in addition to sodium sulfate as the main ingredient, nitrates hindering the polymerizing curing reactions and various other unknown ingredients, while spent resins contain residual cationic exchange groups hindering the polymerizing reaction. Generally, as the acid value of unsaturated liquid polyester resins is lower, the number of terminal alkyd resins is small, formation of nitrates is reduced and the polymerizing curing reaction is taken place more smoothly. In view of the above, radioactive wastes obtained by dry powderization or dehydration of radioactive liquid wastes or spent resins are polymerized with unsaturated liquid polyester resins with the acid value of less than 13 to obtain plastic solidification. Thus, if the radioactive wastes contain a great amount of polymerization hindering material such as NaNO 2 , they can be solidified rapidly and conveniently with no requirement for pre-treatment. (Kamimura, Y.)

Radioactive air emissions 1992 summary

International Nuclear Information System (INIS)

Wahl, L.

1993-10-01

This report summarizes, by radionuclide or product and by emitting facility, the Laboratory's 1992 radioactive air emissions. In 1992, the total activity of radionuclides emitted into the air from Laboratory stacks was approximately 73,500 Ci. This was an increase over the activity of the total 1991 radioactive air emissions, which was approximately 62,400 Ci. Total 1992 Laboratory emissions of each radionuclide or product are summarized by tables and graphs in the first section of this report. Compared to 1991 radioactive air emissions, total tritium activity was decreased, total plutonium activity was decreased, total uranium activity was decreased, total mixed fission product activity was increased, total 41 Ar activity was decreased, total gaseous/mixed activation product (except 41 Ar) activity was increased, total particulate/vapor activation product activity was increased, and total 32 P activity was decreased. Radioactive emissions from specific facilities are detailed in this report. Each section provides 1992 data on a single radionuclide or product and is further divided by emitting facility. For each facility from which a particular radionuclide or product was emitted, a bar chart displays the air emissions of each radionuclide or product from each facility over the 12 reporting periods of 1992, a line chart shows the trend in total emissions of that radionuclide or product from that facility for the past three years, the greatest activity during the 1990--1992 period is discussed, and unexpected or unusual results are noted

DETECTION OF LASALOCID RESIDUES IN THE TISSUES OF BROILER CHICKENS BY A NEW SCREENING TEST TOTAL ANTIBIOTICS

Directory of Open Access Journals (Sweden)

Martin Levkut, ml.

2011-04-01

Full Text Available The aim of the present study was to evaluate the microbial growth inhibition test Total antibiotics for the screening of lasalocid residues in the tissues of broiler chickens after its oral administration in medicated feed. The residues were investigated throughout the 5-day withdrawal period /WP/ and also on day 6 representing the first day following the WP. All broiler chicken tissues were positive for lasalocid. The breast muscle was positive (the presence of residues at/above the detection limit /LOD/ of method up to day 1 of the WP, the thigh muscle, gizzard, heart, skin and fat up to day 3 of the WP and the liver and kidneys up to day 4 of the WP. When evaluating the dubious results (the presence of residues just below the LOD of method, the breast muscle was suspect positive up to day 3 of the WP and the gizzard, skin and fat up to day 4 of the WP. No positive or dubious results were detected on day 5 of the WP. The LOD of Bacillus stearothermophilus var. calidolactis for maduramycin was 500 µg.l-1.doi:10.5219/140

Long lived isotopes in the Chernobyl radioactive cloud at Cracow

International Nuclear Information System (INIS)

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

1988-01-01

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

Handling of Solid Residues

International Nuclear Information System (INIS)

Medina Bermudez, Clara Ines

1999-01-01

The topic of solid residues is specifically of great interest and concern for the authorities, institutions and community that identify in them a true threat against the human health and the atmosphere in the related with the aesthetic deterioration of the urban centers and of the natural landscape; in the proliferation of vectorial transmitters of illnesses and the effect on the biodiversity. Inside the wide spectrum of topics that they keep relationship with the environmental protection, the inadequate handling of solid residues and residues dangerous squatter an important line in the definition of political and practical environmentally sustainable. The industrial development and the population's growth have originated a continuous increase in the production of solid residues; of equal it forms, their composition day after day is more heterogeneous. The base for the good handling includes the appropriate intervention of the different stages of an integral administration of residues, which include the separation in the source, the gathering, the handling, the use, treatment, final disposition and the institutional organization of the administration. The topic of the dangerous residues generates more expectation. These residues understand from those of pathogen type that are generated in the establishments of health that of hospital attention, until those of combustible, inflammable type, explosive, radio-active, volatile, corrosive, reagent or toxic, associated to numerous industrial processes, common in our countries in development

Incorporation of carbohydrate residues into peroxidase isoenzymes in horseradish roots.

Science.gov (United States)

Lew, J Y; Shannon, L M

1973-11-01

Sliced root tissue of the horseradish plant (Armoracia rusticana), when incubated with mannose-U-(14)C, incorporated radioactivity into peroxidase isoenzymes. Over 90% of the radioactivity in the highly purified peroxidase isoenzymes was present in the neutral sugar residues of the molecule, i.e. fucose, arabinose, xylose, mannose. When the root slices were incubated simultaneously with leucine-4,5-(3)H and mannose-U-(14)C, cycloheximide strongly inhibited leucine incorporation into the peptide portion of peroxidase isoenzymes but had little effect on the incorporation of (14)C into the neutral sugars. These results indicated that synthesis of the peptide portion of peroxidase was completed before the monosaccharide residues were attached to the molecule. This temporal relationship between the synthesis of protein and the attachment of carbohydrate residues in the plant glycoprotein, horseradish peroxidase, appears to be similar to that reported for glycoprotein biosynthesis in many mammalian systems.

14C-Profenofos Residues in Milk and Milk Products

International Nuclear Information System (INIS)

Fakhr, I.M.I.; Afifi, L.M.; Fouzy, A.S.M.; Hegazi, B.

1999-01-01

Treatment of lactating goats with only one dose of 14 C-ethoxy profenofos (17.9 mg/Kg) in gelatin capsules and then feeding normally, resulted in the presence of 0.5% of the radioactive insecticide residues in the milk collected through the fourteen successive days. The highest activity level was depicted at the first day and almost disappeared after two weeks. After processing, the analysis of milk products revealed difference in radioactive residue level according to the nature of the product and increased in the order: whey< skim < yoghurt < pasteurized milk < cheese< cream. TLC analysis of milk and milk products revealed the absence of the parent compound and the presence of 4 major metabolites, which were identified by co-chromatography with authentic compounds

Radioactivity of bone cement

International Nuclear Information System (INIS)

Scherer, M.A.; Winkler, R.; Ascherl, R.; Lenz, E.

1993-01-01

A total of 14 samples of different types of bone cement from five different manufacturers were examined for their radioactivity. Each of the investigated bone cements showed a low radioactivity level, i.e. between [de

Evaluation of radioactive inventory of nuclear ship MUTSU

International Nuclear Information System (INIS)

Adachi, M.

1995-01-01

The operation of the Nuclear Ship MUTSU was terminated in January 1992. Radioactivities and dose rates on the surfaces of reactor components were measured in order to estimate the residual radioactive inventory in the MUTSU. The predicted radioactive inventory due to neutron activation was calculated by using a computer code systems. The results show good correlation between predicted and measured values radioactivities in the core baffle plate. The radioactive inventory was estimated to be 8.4 x 10 14 Bq as of 1.5 years from the final shutdown of reactor operation. The contamination in reactor components was estimated from the contamination level measured in the Japan Power Demonstration Reactor (JPDR), from which the dose rates in the reactor room were calculated. The radioactive inventory due to contamination was estimated at 3.4 x 10 10 Bq. Some difference was found between these calculations and measurements. (Author)

Effect of Refining Processes on Magnitude and Nature of Malathion and Carbofuran Residues in Cotton Seed Oil

International Nuclear Information System (INIS)

Zayed, S.M.A.D.; Farghaly, M.; Mahdy, F.

2005-01-01

Cotton seeds obtained from 14 C-carbofuran or 14 C-malathion-treated plants contained 0.25% and 0.11% of the originally applied radioactivity, respectively. The concentration of malathion residues in oil, methanol soluble and in the seed cake amounted to 0.94, 2.6 and 1.7 ppm, respectively. Commercial processing procedures led to a gradual decrease in the total amount of 14 C-residues in oils with aged residues as well as in oil fortified with the radiolabelled insecticides. The refined oil contained only about 20% of the 14 C-residues originally present. The major residue in processed oil contained malathion, malathion monocarboxylic acid and alpha-(O,O-dimethyl phosphorodithio)-propionic acid. The concentration of 14 C-carbofuran residues in cotton seed oil, methanol extract and cake was 1.7, 12.3 and 2.4 ppm, respectively. The main residues in the oil were carbofuran and its phenol. The methanol solubles contained conjugated metabolites, which upon hydrolysis gave 3-hydroxy-carbofuran as a major product. Refinement reduced the residue in oil to 0.26 ppm. The residue in refined oil contained carbofuran and carbofuran phenol as main constituents together with smaller amounts of 3-hydroxy- and 3-keto carbofuran

Assessment of alternatives for long-term management of uranium ore residues and contaminated soils located at DOE's Niagara Falls Storage Site

International Nuclear Information System (INIS)

Merry-Libby, P.

1985-01-01

About 11,000 m 3 of uranium ore residues and 180,000 m 3 of slightly contaminated soils (wastes) are consolidated within a diked containment area at the Niagara Falls Storage Site located about 30 km north of Buffalo, New York. The residues account for less than 6% of the total volume of contaminated materials but almost 99% of the radioactivity. The average radium-226 concentration in the residues is 67,000 pCi/g. The US Department of Energy is considering several alternatives for long-term management of the wastes and residues, including: improvement of the containment at NFSS, modification of the form of the residues, management of the residues separately from the wastes, management of the wastes and residues at another humid site (Oak Ridge, Tennessee) or an arid site (Hanford, Washington), and dispersal of the wastes in the ocean. Potential radiological risks associated with implementation of any of the alternatives are expected to be smaller than the nonradiological risks of occupational and transportation-related injuries and deaths. Dispersal of the slightly contaminated wastes in the ocean is not expected to result in any significant radiological risk to humans. The residues and wastes will remain hazardous for thousands of years. After controls cease, the radioactive materials will eventually be dispersed in the environment. Loss of the earthen covers over the buried materials is predicted to occur from several hundred to more than two million years, depending primarily on the use of the land surface. Groundwater will eventually be contaminated in all alternatives; however, the groundwater pathway is relatively insignificant with respect to radiological risks to the general population. 2 references, 2 figures, 6 tables

Radioactive waste management in West Germany

Energy Technology Data Exchange (ETDEWEB)

Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)

1978-01-01

The technologies developed in West Germany for radioactive waste management are widely reviewed. The first topic in this review paper is the disposal of low- and middle-level radioactive liquid wastes. Almost all these liquid wastes are evaporated, and the typical decontamination factor attained is 10/sup 4/ -- 10/sup 6/. The second topic is the solidification of residuals. Short explanation is given to bituminization and some new processes. The third topic is high-level liquid wastes. Degradation of glass quality due to various radiation is discussed. Embedding of small glass particles containing radioactive wastes into metal is also explained. Disposals of low-level solid wastes and the special wastes produced from reprocessing and mixed oxide fuel fabrication are explained. Final disposal of radioactive wastes in halite is discussed as the last topic. Many photographs are used to illustrate the industrial or experimental use of those management methods.

Safety of radioactive waste management. Proceedings of an international conference

International Nuclear Information System (INIS)

2000-01-01

The principal objective of the Conference was to enable members of the scientific community and representatives of facilities which produce radioactive waste, of bodies responsible for radioactive waste management, of nuclear regulatory bodies and of public interest groups, among others, to engage in an open dialogue. The open dialogue which took place may, by providing policy and decision makers with a basis for political action, prove to be an important step in the search for the international consensus so essential in the area of radioactive waste management. The relevant policies and activities of the IAEA, the European Commission, the OECD Nuclear Energy Agency and the World Health Organization were presented. The evolution, under the aegis of the IAEA, of a de facto international radiation and nuclear safety regime was noted. In the area of radioactive waste safety, this regime consists of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, the body of international waste safety standards established by the IAEA and other international organizations, and the IAEA's mechanisms for providing for the application of those standards. The topics covered by the Conference were: Current international co-operative efforts; Recommendations from the International Commission on Radiological Protection; Recommendations from the International Nuclear Safety Advisory Group; Conclusions and recommendations of the International Symposium on the Restoration of Environments with Radioactive Residues; Siting of radioactive waste management facilities; Participation of interested parties; Legislative and general radiation safety aspects; Removal of material from regulatory control (exclusion, exemption and clearance); Predisposal management (dilution, recycling, transmutation, etc.); Near surface disposal; Residues from the mining and processing of radioactive ores; Long term institutional control; Geological disposal

Influence of humic fractions on retention of isoproturon residues in two Moroccan soils.

Science.gov (United States)

Elkhattabi, Kaouakeb; Bouhaouss, Ahmed; Scrano, Laura; Lelario, Filomena; Bufo, Sabino A

2007-01-01

The influence of different fractions of soil organic matter on the retention of the herbicide isoproturon (IPU) has been evaluated. Water and methanol extractable residues of (14)C labeled isoproturon have been determined in two Moroccan soils by beta -counting-liquid chromatography. The quantification of bound residues in soil and in different fractions of soil humic substances has been performed using pyrolysis/scintillation-detected gas-chromatography. Microbial mineralization of the herbicide and soil organic matter has been also monitored. Retention of isoproturon residues after 30-days incubation ranged from 22% to 32% (non-extractable fraction). The radioactivity extracted in an aqueous environment was from 20% to 33% of the amount used for the treatment; meanwhile, methanol was able to extract another 48%. Both soils showed quantities of bound residues into the humin fraction higher than humic and fulvic acids. The total amount of residues retained into the organic matter of the soils was about 65 % of non-extractable fraction, and this percentage did not change with incubation time; on the contrary, the sorption rate of the retention reaction is mostly influenced by the clay fraction and organic content of the soil. Only a little part of the herbicide was mineralized during the experimental time.

Method and apparatus for evaporating radioactive liquid and calcinating the residue

International Nuclear Information System (INIS)

Sridhar, T.S.

1984-01-01

This invention provides an apparatus and a process for evaporating liquid wastes and calcining the residue. The liquid is sprayed against a hollow, rotating heated cylinder within a casing. The dried residue is scraped from the rotating cylinder and released through a valve at the bottom of the casing, while the effluent gas is filtered

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)

Bound residues in corn plants treated with 14C-atrazine and bioavailability to rats

International Nuclear Information System (INIS)

Khan, S.U.

1986-01-01

Corn plants, about 3.5 months old and treated with 14 C-atrazine, were used in an experiment in which the aerial portion of the plants was exhaustively extracted with solvents. The extracted dried material containing bound 14 C-residues was fed to rats. The extracted aerial portion of control corn plants fortified with 14 C-atrazine was also fed to rats. After four days, 88% and 32% of the radioactivity was excreted in the faeces, and 10% and 60% radioactivity was voided in the urine from rats fed plant material containing bound and fortified 14 C-residues, respectively. The data suggest that the bioavailability to rats of bound 14 C-residues in corn material is low. (author)

Calculation of total number of disintegrations after intake of radioactive nuclides using the pseudo inverse matrix

International Nuclear Information System (INIS)

Noh, Si Wan; Sol, Jeong; Lee, Jai Ki; Lee, Jong Il; Kim, Jang Lyul

2012-01-01

Calculation of total number of disintegrations after intake of radioactive nuclides is indispensable to calculate a dose coefficient which means committed effective dose per unit activity (Sv/Bq). In order to calculate the total number of disintegrations analytically, Birch all's algorithm has been commonly used. As described below, an inverse matrix should be calculated in the algorithm. As biokinetic models have been complicated, however, the inverse matrix does not exist sometime and the total number of disintegrations cannot be calculated. Thus, a numerical method has been applied to DCAL code used to calculate dose coefficients in ICRP publication and IMBA code. In this study, however, we applied the pseudo inverse matrix to solve the problem that the inverse matrix does not exist for. In order to validate our method, the method was applied to two examples and the results were compared to the tabulated data in ICRP publication. MATLAB 2012a was used to calculate the total number of disintegrations and exp m and p inv MATLAB built in functions were employed

Radioactive waste treatment apparatus

International Nuclear Information System (INIS)

Abrams, R.F.; Chellis, J.G.

1983-01-01

Radioactive waste treatment apparatus is disclosed in which the waste is burned in a controlled combustion process, the ash residue from the combustion process is removed and buried, the gaseous effluent is treated in a scrubbing solution the pH of which is maintained constant by adding an alkaline compound to the solution while concurrently extracting a portion of the scrubbing solution, called the blowdown stream. The blowdown stream is fed to the incinerator where it is evaporated and the combustibles in the blowdown stream burned and the gaseous residue sent to the scrubbing solution. Gases left after the scrubbing process are treated to remove iodides and are filtered and passed into the atmosphere

Study of extraterrestrial disposal of radioactive wastes. Part 3: Preliminary feasibility screening study of space disposal of the actinide radioactive wastes with 1 percent and 0.1 percent fission product contamination

Science.gov (United States)

Hyland, R. E.; Wohl, M. L.; Finnegan, P. M.

1973-01-01

A preliminary study was conducted of the feasibility of space disposal of the actinide class of radioactive waste material. This waste was assumed to contain 1 and 0.1 percent residual fission products, since it may not be feasible to completely separate the actinides. The actinides are a small fraction of the total waste but they remain radioactive much longer than the other wastes and must be isolated from human encounter for tens of thousands of years. Results indicate that space disposal is promising but more study is required, particularly in the area of safety. The minimum cost of space transportation would increase the consumer electric utility bill by the order of 1 percent for earth escape and 3 percent for solar escape. The waste package in this phase of the study was designed for normal operating conditions only; the design of next phase of the study will include provisions for accident safety. The number of shuttle launches per year required to dispose of all U.S. generated actinide waste with 0.1 percent residual fission products varies between 3 and 15 in 1985 and between 25 and 110 by 2000. The lower values assume earth escape (solar orbit) and the higher values are for escape from the solar system.

The Effect of Processing on 14C- Chlofenvinphos Residues in Maize Oil and Bioavailability of its Cake Residues on Rats

International Nuclear Information System (INIS)

Mahdy, F.; El-Maghraby, S.

2008-01-01

Maize seed obtained from 14 C-chlofenvinphos treated plants contained 0.12 % of the applied dose. The insecticide residues in crude oil, methanol and coke amounted to 10 %, 6 % and 69 %, respectively of original residues inside the seeds.The 14 C activity in the crude oil could be a gradual reduced by the refining processes. The alkali treatment and bleaching steps are more effective steps in the refining processes remove about (63 %). The refined oil contained only about 17 % of the 14 C-residues originally present. The major residues in processed oil contain parent compound, in addition to five metabolites of the insecticide. When rats fed the extracted seeds (cake), the bound residues were found to be considerably bioavailable. After feeding rats for 5 days with the cake, a substantial amount of 14 C-residues was eliminated in the urine (59.5 %), while about 20 % was excreted in the feces. About 15 % of the radioactivity was distribution among various organs

Depletion of isoeugenol residues from the fillet tissue of AQUI-S™ exposed rainbow trout (Oncorhynchus mykiss)

Science.gov (United States)

Meinertz, Jeffery R.; Schreier, Theresa M.

2009-01-01

There is a critical need in U.S. public aquaculture and fishery management for an approved sedative that allows for the immediate release of fish after sedation. AQUI-STM is a fish anesthetic/sedative approved for use in several countries and until recently was being developed in the U.S. as a sedative for immediate release of fish after sedation. The U.S. National Toxicology Program reported that isoeugenol (the active ingredient in AQUI-STM) exposed male mice showed clear evidence of carcinogenicity, therefore efforts within the U.S. Department of Interior to develop AQUI-STM as a sedative that allows for immediate release ceased. Despite the ruling, AQUI-STM still has the potential to be approved as an anesthetic with a short withdrawal time. Among the data required to gain approval for use in the U.S. are data describing the composition and depletion of all AQUI-STM residues from fish fillet tissue. A total residue depletion study for AQUI-STM was conducted by exposing market-sized rainbow trout, Oncorhynchus mykiss (mean weight, 502.7 ± 54 g; s.d.) to 8.9 mg/L of 14C-[URL]-isoeugenol for 60 min in 17 °C water. The 14C-[URL]-isoeugenol was mixed with a surfactant resulting in a mixture that mimicked AQUI-STM. Groups of fish (n = 6) were sampled immediately after the exposure (0-h sample group) and at 0.5, 1, 2, and 4 h thereafter. Total isoeugenol-equivalent residue concentrations in the fillet tissue were determined by oxidizing triplicate subsamples of homogenized skin-on fillet tissue from each fish to 14CO2 and enumerating the radioactivity by static liquid scintillation counting. Isoeugenol concentrations in fillet tissue were determined by extracting homogenized fillet tissue with solvents and determining the isoeugenol concentrations in the extracts with high performance liquid chromatography techniques. The mean total isoeugenol-equivalent residue concentrations in the 0, 0.5, 1, 2, and 4-h sample groups were 55.4, 32.0, 19.8, 11

Stowing of radioactive materials package during road transport on vehicles of a total weight under 38 tons

International Nuclear Information System (INIS)

Gilles, P.; Chevalier, G.; Pouard, M.

1985-01-01

Results of testing allow the formulation of recommendations for stowing radioactive material packaging for severe accidental conditions during land transport. For frontal impact kinetic energy acquired by deceleration should be totally absorbed by the packaging, as this energy is proportional to its mass it will stay on the vehicle. For side impact, the packaging should yield because kinetic energy to absorb, if fasteners are not deformed before rupture, can be largely over the packaging mass and damage could be very severe

Total sulfur determination in residues of crude oil distillation using FT-IR/ATR and variable selection methods

Science.gov (United States)

Müller, Aline Lima Hermes; Picoloto, Rochele Sogari; Mello, Paola de Azevedo; Ferrão, Marco Flores; dos Santos, Maria de Fátima Pereira; Guimarães, Regina Célia Lourenço; Müller, Edson Irineu; Flores, Erico Marlon Moraes

2012-04-01

Total sulfur concentration was determined in atmospheric residue (AR) and vacuum residue (VR) samples obtained from petroleum distillation process by Fourier transform infrared spectroscopy with attenuated total reflectance (FT-IR/ATR) in association with chemometric methods. Calibration and prediction set consisted of 40 and 20 samples, respectively. Calibration models were developed using two variable selection models: interval partial least squares (iPLS) and synergy interval partial least squares (siPLS). Different treatments and pre-processing steps were also evaluated for the development of models. The pre-treatment based on multiplicative scatter correction (MSC) and the mean centered data were selected for models construction. The use of siPLS as variable selection method provided a model with root mean square error of prediction (RMSEP) values significantly better than those obtained by PLS model using all variables. The best model was obtained using siPLS algorithm with spectra divided in 20 intervals and combinations of 3 intervals (911-824, 823-736 and 737-650 cm-1). This model produced a RMSECV of 400 mg kg-1 S and RMSEP of 420 mg kg-1 S, showing a correlation coefficient of 0.990.

Marking with radioactive iodine of a plasma substitute and preliminary essays of his kinetic behaviour in rats

International Nuclear Information System (INIS)

Cova, Wilma Guimaraes

1973-01-01

A blood plasma substitute (Haem accel - PGO), which has as a base a degraded and polymerized gelatin, was labelled with radioactive iodine (I-131) and preliminary essays of its kinetic behavior was done. We have used the labelling method of McFarlaner. The results obtained - radiochemical yield and purity - were favorable. The kinetic behaviour the residual radioactivity studied by measuring the residual radioactivity of the body and excreta in groups of male Wistar rats for a maximum period of 150 hours. These results have shown and excellent correlation for a two components exponential function's adjustment, suggesting therefore a bi compartmental mathematical model. (author)

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

Treatment of low-and intermediate-level radioactive waste concentrates

International Nuclear Information System (INIS)

1968-01-01

The report of a panel convened by the IAEA in Vienna, 2-6 May 1966. Thirteen experts from eight countries and one international organization attended the meeting. This report is related to treatment and radioactive sludges or residues resulting from treatment and purification of radioactive wastes. It includes: (i) concentration by evaporation; (ii) filtration; (iii) insolubilization by means of bitumen; (iv) use of cement or cement-vermiculite. 31 refs, 34 figs, 14 tabs

Revk - a Tool for the Fulfilment of Requirements from National Rules for Tracking and Documentation of Radioactive Residual Material and Radioactive Waste

International Nuclear Information System (INIS)

Hartmann, B.; Haeger, M.; Gruendler, D.

2006-01-01

According to the German Radiation Protection Ordinance treatment, storage, whereabouts of radioactive material etc. have to be documented. Due to legal requirements an electronic documentation system for radioactive waste has to be installed. Within the framework of the currently largest decommissioning project of nuclear facilities by Energiewerke Nord GmbH, a material flow-waste tracking and control system (ReVK) has been developed, tailored to the special needs of the decommissioning of nuclear facilities. With this system it is possible to record radioactive materials which can be released after treatment or decay storage for restricted and unrestricted utilization. Radioactive waste meant for final storage can be registered and documented as well. Based on ORACLE, ReVK is a client/server data base system with the following modules: 1. data registration, 2. transport management, 3. waste tracking, 4. storage management, 5. container management, 6. reporting, 7. activity calculation, 8. examination of technical acceptance criteria for storages and final repositories. Furthermore ReVK provides a multitude of add-ons to meet special user needs, which enlarge the spectrum of application enormously. ReVK is validated and qualified, accepted by experts and authorities and fulfils the requirements for a radioactive waste documentation system. (authors)

Pathways analysis and radiation-dose estimates for radioactive residues at formerly utilized MED/AEC sites

Energy Technology Data Exchange (ETDEWEB)

Gilbert, T.L.; Chee, P.C.; Knight, M.J.; Peterson, J.M.; Roberts, C.J.; Robinson, J.E.; Tsai, S.Y.H.; Yuan, Y.C.

1983-03-01

Methods of analysis are developed for estimating the largest individual radiation dose that could result from residual radioactivity at sites identified by the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy. Two unique aspects of the methods are (1) a systematic structuring of the radiation pathways analysis into source terms, source-to-exposure analysis, and exposure-to-dose analysis, and (2) the systematic use of data on the average concentrations of naturally occurring radionuclides in soil, food, and the human body in order to assess the validity of model calculations and obtain more realistic values. The methods are applied to a typical FUSRAP site in order to obtain generic source-to-dose (D/S) conversion factors for estimating the radiation dose to the maximally exposed individual from a known concentration of radionuclides in the soil. The D/S factors are used to derive soil guidelines, i.e., the limiting concentrations of radionuclides at a typical FUSRAP site that are unlikely to result in individual dose limits that exceed generally accepted radiation protection standards. The results lead to the conclusion that the soil guidelines should not exceed 17, 75, and 300 pCi/g for Ra-226, U-238, and Th-230, respectively.

Pathways analysis and radiation-dose estimates for radioactive residues at formerly utilized MED/AEC sites

International Nuclear Information System (INIS)

Gilbert, T.L.; Chee, P.C.; Knight, M.J.; Peterson, J.M.; Roberts, C.J.; Robinson, J.E.; Tsai, S.Y.H.; Yuan, Y.C.

1983-03-01

Methods of analysis are developed for estimating the largest individual radiation dose that could result from residual radioactivity at sites identified by the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy. Two unique aspects of the methods are (1) a systematic structuring of the radiation pathways analysis into source terms, source-to-exposure analysis, and exposure-to-dose analysis, and (2) the systematic use of data on the average concentrations of naturally occurring radionuclides in soil, food, and the human body in order to assess the validity of model calculations and obtain more realistic values. The methods are applied to a typical FUSRAP site in order to obtain generic source-to-dose (D/S) conversion factors for estimating the radiation dose to the maximally exposed individual from a known concentration of radionuclides in the soil. The D/S factors are used to derive soil guidelines, i.e., the limiting concentrations of radionuclides at a typical FUSRAP site that are unlikely to result in individual dose limits that exceed generally accepted radiation protection standards. The results lead to the conclusion that the soil guidelines should not exceed 17, 75, and 300 pCi/g for Ra-226, U-238, and Th-230, respectively

Study on recovering directly the commercial cerium oxide and total of residue rare earths from Dongpao bastnasite concentrate

International Nuclear Information System (INIS)

Nguyen Trong Hung; Nguyen Thanh Chung; Luu Xuan Dinh

2003-01-01

A technology for decomposition roasting and sequential leaching processes of Dong Pao bastnasite concentrate to recover directly commercial cerium oxide and total of residue rare earth elements from the leaching solution of the roasted product have been investigated. The bastnasite concentrate is initially roasted at temperature range of 600 - 650 degC and for time of 4 hrs in order to decompose and convert the hardly soluble carbonate forms of ore into easily soluble oxide. The roasted solid is then leached with sulfuric acid solution of 6N at 60 degC for 4 hrs to convert rare earths in oxide and fluoride form into rare earth sulfate. The recovery yield of rare earths of these stages is more than 95%. The attention has especially been paid on recovering directly the commercial cerium oxide and total of residue rare earth element from the above leaching solution. Complex ions of CeSO 4 2+ , Ce(SO 4 ) 2 , Ce(SO 4 ) 3 2- and Ce(SO 4 ) 4 4- exist in aqueous solution of cerium (IV) sulfate. Based on the property, the method of ion - sieve with DOWEX cation resin column has been applied to estimating separation of the ceric complex anions from Ln(III). The survey showed that most of the ceric complex anions are separated from total of residue rare earths. The latter which are absorbed in the cation column are recovered by elution of HCl of 4N. The recovery yield of cerium can only be reached 20% but the purity of that is very high, can be reached 99.6%. About 5 kg of CeO 2 of high grade and 5 kg of TREO of commercial specification have been produced. (author)

The measurement of radioactivity in tomatoes cultivated on mining residues from the Oka niobium mining community

International Nuclear Information System (INIS)

Boulet, M.; Boudreau, A.; Roy, J.C.

1983-01-01

The radioactivity contained in the tailings of a niobium mine in the Oka region, Quebec, was the object of concern for the population of the area in 1979. To find the impact of these tailings on fruit and vegetables grown in this environment, an investigation of the radioactivity found on tomatoes grown in green houses in niobium tailings and in vermiculites was undertaken. The tailings contained a high level of natural radioactivity and a small amount of 137 Cs while the vermiculites has a very low level of natural radioactivity and an appreciable amount of 137 Cs. Cesium-137 was the only nuclide detected in tomato ashes in measurable quantity. Absence of natural radioactivity is explained by its presence as insoluble minerals. (author) [fr

General Atomic's radioactive gas recovery system

International Nuclear Information System (INIS)

Mahn, J.A.; Perry, C.A.

1975-01-01

General Atomic Company has developed a Radioactive Gas Recovery System for the HTGR which separates, for purposes of retention, the radioactive components from the non-radioactive reactor plant waste gases. This provides the capability for reducing to an insignificant level the amount of radioactivity released from the gas waste system to the atmosphere--a most significant improvement in reducing total activity release to the environment. (U.S.)

Evaluation of dose due to the liberation of the radioactive content present in systems of final disposal of radioactive residues; Evaluacion de la dosis debida a la liberacion del contenido radiactivo presente en sistemas de disposicion final de residuos radiactivos

Energy Technology Data Exchange (ETDEWEB)

Amado, V; Lopez, F [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, Ciudad Autonoma de Buenos Aires (C1429BNP) (Argentina)

2006-07-01

The disposal systems of radioactive residuals well-known as repositories near to the surface, are used to dispose residuals that can contain high concentrations of radionuclides of period of short semi disintegration, which they would decay at levels radiologically insignificant in some few decades or in some centuries: and acceptably low concentrations of radionuclides of period of long semi disintegration. The dose that would receive the critic group due to these systems it could be increased by cause of discreet events that affect the foreseen retard time, or by the gradual degradation of the barriers. To this last case it contributes the presence of water, because it implies leaching and dissolution that can give place to radionuclide concentrations in the underground water greater to the prospective ones. The dosimetric evaluation is important because it offers useful objective information to decide if a given repository is adjusted to the purposes of its design and it fulfills the regulatory requirements. In this work a simplified evaluation of the dose that would receive the critic group due to the liberation of contained radionuclides in a hypothetical system of final disposition of radioactive residuals is presented. For it, they are considered representative values of the usually contained activities in this type of systems and they are carried out some approaches of the source term. The study is developed in two stages. In the first one, by means of the Radionuclide pollutant scattering pattern in phreatic aquifers (DRAF) it is considered the scattering of the pollutants in the phreatic aquifer, until the discharge point in the course of the nearest surface water. This model, developed originally in the regulatory branch of the National Commission of Argentine Atomic Energy (CNEA); it solves the transport equation of solutes in porous means in three dimensions, by the finite differences method having in account the soil retention and the radioactive

Induced fission track distribution from highly radioactive particles in fallout materials

International Nuclear Information System (INIS)

Hashimoto, Tetsuo; Okada, Tatemichi

1987-01-01

Some highly radioactive fallout particles (GPs) from the 19th Chinese nuclear detonation were followed to the neutron irradiation in a reactor after sandwiched with mica detectors. The interesting star-like fission track patterns were revealed on the etched surface of the mica detectors. The simple chemical separation procedure for the GPs was applied for the separation of U and Pu as fissile elements and the both resultant fractions were examined with the similar high sensitive fission tracking detection. Subsequently, a representative track pattern from a black spherical particle was subjected to the determination of fissile nuclide content; comparing the total fission events evaluated on the basis of the numerical calculation of track densities with the total thermal neutron fluence. The results implied that the uranium is responsible for the main fissile nuclide remaining within a particle as unfissioned fractions and should be certainly enriched with respect to U-235 within such small fallout particles. This sophisticated method was also applied to determine the dead GPs, which have been highly radioactive particles just after the detonations, in the rain and snow-residual materials. Many induced star-like fission tracks verified certainly that there remains a lot of dead particles in the atmosheric environment till nowadays. (author)

Efficiency of the refining processes in removing 14C-dichlorvos residues in soybean oil

International Nuclear Information System (INIS)

Soliman, S.M.

2006-01-01

Crude soybean oil extracted from grains treated with 14 C-dichlorvos at a dose 24 mg insecticide / kg seeds and stored for 30 weeks was subjected to different refining processes such as alkali treatment, bleaching, winterization and deodorization. The effect of the refining processes on the nature and magnitude of the originally present residues was investigated. The insecticide residues in crude oil and cake amounted to 9.5% and 55% , respectively, of original residues inside the seeds. Extraction of the seeds with hexane gave crude oil with 9.5 % of original residues in seeds. The l4 C-activity in the crude stored Soya beans oil could be reduced by about 82% of radioactivity originally present in crude oil eliminated by simulated commercial processes locally used for oil refining. A high percentage of the residues (50-55%) were eliminated during alkali treatment and bleaching. Refining of soybeans oil fortified with '1 4 C-dichlorovos. The final refined oil had only 13% of the radioactivity originally present, mainly in the form of dichlorvos, dimethyl and monomethyl phosphate in addition to desmethyl dichlorvos in oil with aged residues

Evaluation of radon and radioactivity level in phosphorite area in Guizhou

International Nuclear Information System (INIS)

Li Zhou; Yang Zhong; Wei Tao; Zhang Xiaole; Yu Lixin; Tian Zhujuan

2006-01-01

Objective: To study and assess atmospheric radon and radioactive levels in one of phosphorite area in Guizhou province. Methods: To monitor and analyze the external irradiation level, atmospheric radon, nuclide levels, and water total radioactivity on the spot and in the laboratory. Results: External irradiation level is 7-18 x 10 -8 Gy/h, the mean value is 12 x 10 -8 Gy/h, atmospheric radon concentration is 105-246 Bq/m 3 , ore 226 Ra nuclide levels are between 156.7-372.3 Bq/kg, the mean value is 222.6 Bq/kg, the maximum total radioactivity levels of mine water are total α=0.175 Bq/L and total β=0.374 Bq/L, the total radioactivity levels of drinking water is not more than total α=0.0327 Bq/L, total β=0.174 Bq/L. Conclusion: Radioactivity levels accord with the relevant national standards. There were remarkable correlation in the total radioactivity levels of mine water and drinking water. The radon concentration in well air is not up to the point of reach intervention level. (authors)

Radiation surveys of radioactive material shipments

International Nuclear Information System (INIS)

Howell, W.P.

1986-07-01

Although contractors function under the guidance of the Department of Energy, there is often substantial variation in the methods and techniques utilized in making radiation measurements. When radioactive materials are shipped from one contractor to another, the measurements recorded on the shipping papers may vary significantly from those measured by the receiver and has been a frequent cause of controversy between contractors. Although significant variances occur in both measurements of radiation fields emanating from shipment containers and measurements of residual radioactivity on the surfaces of the containers, the latter have been the most troublesome. This report describes the measurement of contamination on the exterior surfaces of shipment containers

Tritium labeling of gonadotropin releasing hormone in its proline and histidine residues

International Nuclear Information System (INIS)

Klauschenz, E.; Bienert, M.; Egler, H.; Pleiss, U.; Niedrich, H.; Nikolics, K.

1981-01-01

3,4-dehydroproline9-GnRH prepared by solid phase peptide synthesis was tritiated catalytically under various conditions yielding 3H-GnRH with specific radioactivities in the range from 35-60 Ci/mmol and full LH releasing activity in vitro. Using palladium/alumina catalyst, the tritiation of the double bond occurs within ten minutes. Investigation of the tritium distribution between the amino acid residues showed a remarkably high incorporation of tritium into the histidine residue (11 to 37%). On the basis of this observation, the tritium labeling of GnRH and angiotensin I by direct catalytic hydrogen-tritium exchange was found to be useful for the labeling of these peptides at remarkably high specific radioactivity

Optimisation of recovery protocols for double-base smokeless powder residues analysed by total vaporisation (TV) SPME/GC-MS.

Science.gov (United States)

Sauzier, Georgina; Bors, Dana; Ash, Jordan; Goodpaster, John V; Lewis, Simon W

2016-09-01

The investigation of explosive events requires appropriate evidential protocols to recover and preserve residues from the scene. In this study, a central composite design was used to determine statistically validated optimum recovery parameters for double-base smokeless powder residues on steel, analysed using total vaporisation (TV) SPME/GC-MS. It was found that maximum recovery was obtained using isopropanol-wetted swabs stored under refrigerated conditions, then extracted for 15min into acetone on the same day as sample collection. These parameters were applied to the recovery of post-blast residues deposited on steel witness surfaces following a PVC pipe bomb detonation, resulting in detection of all target components across the majority of samples. Higher overall recoveries were obtained from plates facing the sides of the device, consistent with the point of first failure occurring in the pipe body as observed in previous studies. The methodology employed here may be readily applied to a variety of other explosive compounds, and thus assist in establishing 'best practice' procedures for explosive investigations. Copyright © 2016 Elsevier B.V. All rights reserved.

Studies of radioactivity from nuclear explosions for peaceful purposes

Energy Technology Data Exchange (ETDEWEB)

Siddons, R A [AWRE, Aldermaston (United Kingdom)

1970-05-01

Estimates are made of the extent and duration of hazards from radioactivity to the general public due to fallout from a cratering explosion. The nuclear explosive is assumed to be 'clean' in the sense that only a small fraction of the yield is derived from fission. Hypothetical examples take an explosive of total yield 100 kT, of which 10 kT, 1 kT and zero - the ultimate in cleanliness - are derived from fission. The maximum permitted level to the public is taken as 0.5 rem in a period of one year. Sources of activity considered are fission products, residual thermonuclear material (tritium), neutron induced activity in the device materials and neutron induced activity in the surrounding rock. Estimates of the production are made, and are associated with a distribution function derived from the Sedan fallout measurements. The hazards from radioactivity associated with the creation of a storage reservoir for natural gas have also been considered. In this case the main problem is contamination of the product by tritium left in the chimney. The possibility of flushing out this tritium with water is discussed. (author)

Studies of radioactivity from nuclear explosions for peaceful purposes

International Nuclear Information System (INIS)

Siddons, R.A.

1970-01-01

Estimates are made of the extent and duration of hazards from radioactivity to the general public due to fallout from a cratering explosion. The nuclear explosive is assumed to be 'clean' in the sense that only a small fraction of the yield is derived from fission. Hypothetical examples take an explosive of total yield 100 kT, of which 10 kT, 1 kT and zero - the ultimate in cleanliness - are derived from fission. The maximum permitted level to the public is taken as 0.5 rem in a period of one year. Sources of activity considered are fission products, residual thermonuclear material (tritium), neutron induced activity in the device materials and neutron induced activity in the surrounding rock. Estimates of the production are made, and are associated with a distribution function derived from the Sedan fallout measurements. The hazards from radioactivity associated with the creation of a storage reservoir for natural gas have also been considered. In this case the main problem is contamination of the product by tritium left in the chimney. The possibility of flushing out this tritium with water is discussed. (author)

A study on the treatment of radioactive slurry liquid waste

International Nuclear Information System (INIS)

Jeong, Gyeong Hwan; Chung, U. S.; Baik, S. T.; Park, S. K.; Moon, J.S.; Jung, K.J.

1998-12-01

The influence of anionic flocculants on the dewatering of radioactive slurries has been investigated in a laboratory-scale vacuum filtration unit. Simultaneously the influence of certain surfactants on the dewatering of radioactive slurries with anionic flocculants has also been investigated. Test results show that the flocculated filter cake generally contains higher residual water than the unflocculated cake. The non-ionic surfactant Triton X-100 was effective in reducing the moisture content of the cake

A study on the treatment of radioactive slurry liquid waste

Energy Technology Data Exchange (ETDEWEB)

Jeong, Gyeong Hwan; Chung, U. S.; Baik, S. T.; Park, S. K.; Moon, J.S.; Jung, K.J

1998-12-01

The influence of anionic flocculants on the dewatering of radioactive slurries has been investigated in a laboratory-scale vacuum filtration unit. Simultaneously the influence of certain surfactants on the dewatering of radioactive slurries with anionic flocculants has also been investigated. Test results show that the flocculated filter cake generally contains higher residual water than the unflocculated cake. The non-ionic surfactant Triton X-100 was effective in reducing the moisture content of the cake.

Removal of organics from radioactive waste. V. 2

International Nuclear Information System (INIS)

Williams, J.; Kitchin, J.; Burton, W.H.

1989-05-01

This report reviews the available literature concerning the removal of organic substances from radioactive waste streams. A substantial portion of low level wastes generated in the various parts of the nuclear fuel cycle, nuclear laboratories and other places where radionuclides are used for research, industrial medical and defense related activities is organic (paper, wood, plastics, rubber etc.) and combustible. These combustible wastes can be processed by incineration. Incineration converts combustible wastes into radioactive ashes and residues that are non-flammable, chemically inert and more homogenous than the initial waste. (author)

World ocean and radioactive wastes

International Nuclear Information System (INIS)

Kiknadze, O.E.; Sivintsev, Yu.V.

2000-01-01

The radioecological situation that took shape in the Arctic, North Atlantic Ocean and Far East regions as a result of radioactive waste marine disposal was assessed. Accurate account of radionuclides formation and decay in submerged water-water reactors of nuclear submarines suggests that total activity of radioactive waste disposed near the Novaya Zemlya amounted to 107 kCi by the end of 1999. Activity of radioactive waste disposed in the North Atlantic currently is not in excess of 430 kCi. It is pointed out that the Far East region heads the list in terms of total activity disposed (529 kCi). Effective individual dose for critical groups of population in the Arctic, North Atlantic and Far East regions was determined. The conclusion was made that there is no detrimental effect of the radioactive waste disposed on radioecological situation in the relevant areas [ru

Uses of ANSI/HPS N13.12-1999, "Surface and Volume Radioactivity Standards for Clearance" and Comparison with Existing Standards

Energy Technology Data Exchange (ETDEWEB)

Stansbury, Paul S.; Strom, Daniel J.

2001-04-30

In August of 1999, the American National Standards Institute (ANSI) approved a standard for clearance of materials contaminated with residual levels of radioactivity. "Clearance," as used in the standard, means the movement of material from the control of a regulatory agency to a use or disposition that has no further regulatory controls of any kind. The standard gives derived screening levels (DSLs) in Bq/g and Bq/cm2 for 50 radionuclides. Items or materials with residual surface and volume radioactivity levels below the DSLs can be cleared, that is, managed without regard to their residual radioactivity. Since federal agencies are to use voluntary, industry standards developed by the private sector whenever possible, the standard should play an important role in DOE's regulatory process. The thrust of this report is to explain the standard, make simple observations on its usefulness to DOE, and to explore uses of the standard within DOE facilities beyond the clearance of radioactive materials.

Radioactivity in food crops

International Nuclear Information System (INIS)

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

1983-05-01

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

Classification of radioactive wastes produced by the nuclear industry

International Nuclear Information System (INIS)

2013-01-01

This document first indicates the origins of radioactive wastes (mainly electronuclear industry), and the composition of spent fuel, and that only fission products and minor actinides are considered as radioactive wastes whereas uranium and plutonium can be used as new fuel after recycling. The classification of radioactive wastes is indicated in terms of radioactivity level and radionuclide half-life: high level (0.2 per cent of the total waste volume but 96 per cent of total waste radioactivity), medium level long life (3 per cent of volume, 4 per cent of radioactivity), low level long life (7 per cent of volume, 0.1 per cent of radioactivity), low and medium level and short life (63 per cent of volume and 0.02 per cent of radioactivity), very low level (27 per cent of volume and less than 0.01 per cent of radioactivity). An overview of radioactive waste processing and storage in France is presented for each category. Current and predicted volumes are indicated for each category. The main challenges are briefly addressed: spent fuel recycling, waste valorisation by fourth-generation reactors. Processing locations in France and in the World are indicated. Some key figures are provided: 2 kg of radioactive waste are produced per inhabitant and per year, and waste management costs represent 5 per cent of the total cost of produced electricity

Transport of radioactive waste in Germany - a survey

International Nuclear Information System (INIS)

Alter, U.

1995-01-01

The transport of radioactive waste is centralised and coordinated by the German Railway Company (Deutsche Bahn AG, DB) in Germany. The conditioning of radioactive waste is now centralised and carried out by the Gesellschaft fuer Nucklear Service (GNS). The Germany Railway Company, DB, is totally and exclusively responsible for the transport, the GNS is totally and exclusively responsible for the conditioning of radioactive waste. The German Railway Company transports all radioactive waste from nuclear power plants, conditioning facilities and the existing intermediate storage facilities in Germany. In 1992 nearly 177 shipments of radioactive waste were carried out, in 1991 the total amount was 179 shipments. A brief description of the transport procedures, the use of different waste packages for radioactive waste with negligible heat generation and the transport routes within Germany will be given. For this purpose the inspection authorities in Germany have used a new documentation system, a special computer program for waste flow tracking and quality assurance and compliance assurance, developed by the electrical power companies in Germany. (Author)

Radioactive materials in construction projects

International Nuclear Information System (INIS)

Herrmann, Ralf; Ohlendorf, Frank; Kaltz, Andrea Christine

2014-01-01

Till 1990 residues often of the former uranium mining were partly used as building material for road construction, terrain compensation and house construction in Saxony. These recommendations for action are addressed to applicants, planners and building constructors in the engineering and construction sector. It provides information for planning, preliminary investigations, applications, construction supervision related to radiation protection measures and documentation of construction projects where radioactive materials are expected.

Radioactive background in principal components of the Jihlava River ecosystem

International Nuclear Information System (INIS)

Stanek, Z.; Penaz, M.; Trnkova, J.; Wohlgemuth, E.

1980-01-01

In 1976 through to 1978, the radioactive background was investigated in the various components of the Jihlava River ecosystem. The investigations involved total β-activity, 40 K, residual β-activity, sup(nat)U, 226 Ra and, in some of the samples, also 210 Pb, 90 Sr and 137 Cs. The analyses included water, bottom sediments, samples of aquatic macrophytes (Batrachium fluitans), samples of aquatic invertebrates (Herpobdella octoculata, Anodonta cygnea, Asellus aquaticus, larval Ephemeroptera, larval Trichoptera, exuviae of pupae of Chironomidae) and samples of the tissues of 8 species of fishes (Salmo trutta m. fario, Cyprinus carpio, Rutilus rutilus, Leuciscus cephalus, Leuciscus leuciscus, Chondrostoma nasus, Gobio gobio, Barbus barbus). The activity of the radionuclides under study corresponded to the values reported for uncontaminated streams. (author)

Cleanup of radioactive mud spill U20aa postshot drilling site NTS

International Nuclear Information System (INIS)

Straume, T.; Kellner, C.R.; Oswald, K.M.

1977-03-01

Radioactive decontamination of a large rugged terrain on the NTS (Area 20) was undertaken during the Summer of 1976. Several decontamination methods were used and their effectiveness, as measured by the fraction of radioactivity remaining (FR), ranged from 10 -1 to 10 -3 , depending upon the method used and type of terrain. Front end loading was most efficient in large relatively flat areas of fine grain, compact dirt with an FR of about 10 -2 . Shoveling and bagging achieved FRs of 10 -2 in locations of fine grain, compact dirt. However, if dirt was coarse grain or gravel-like, the contaminated mud/water had seeped to considerable depths, making shoveling impractical. Flushing with water was the method chosen for rocky surfaces and was the primary method of decontamination in Area 4. FRs down to 10 -3 were achieved on smooth surfaces and about 10 -1 in cracks. Vacuuming was very effective in flat areas with fine grain compact dirt achieving FRs down to 10 -3 , but was a very slow process compared to front end loading. Approximately 900 man days were expended on this cleanup, and 2584 yd 3 of contaminated dirt were removed. A similar amount of clean dirt was transported from about two miles away to cover the crater burial site, mud sump, and areas containing residual radiation above 1 mrem/h contact. Total quantity of residual radioactivity present 6 months following the spill and after decontamination was estimated as 900 millicuries of 106 Ru/Rh and 0.034 millicuries 103 Ru. No person was exposed to doses of radiation (external or internal) above the maximum allowable limits listed in ERDAM 0524. Estimates based upon hand dose measurements indicate that no individual should have received more than 584 mrem to hands

Image findings of a false positive radioactive iodine-131 uptake mimicking metastasis in pulmonary aspergillosis identified on single photon emission computed tomography-computed tomography

Directory of Open Access Journals (Sweden)

Kamaleshwaran Koramadai Karuppusamy

2015-01-01

Full Text Available High doses of iodine-131 are commonly used in patients with differentiated thyroid cancer after total or subtotal thyroidectomy, in order to ablate the remaining cancer or normal thyroid tissue. Multiple different false-positive scans can occur in the absence of residual thyroid tissue or metastases. The authors present a case of abnormal uptake of radioactive iodine in the aspergilloma, potentially masquerading as pulmonary metastases.

Radioactivity in Dutch consumer products

CERN Document Server

Janssen, M P M

2002-01-01

This study took place within the framework of a general update of the average radiation dose for the Dutch population. It focuses on consumer products in which radionuclides have been intentionally incorporated and on radiation-emitting devices that can be supplied to members of the public without special surveillance. Eleven consumer products were studied in more detail. The radiation from these products determined 90% of the total collective dose due to consumer products in the Netherlands in 1988. Individual and collective doses are presented here for each product. The total collective dose has decreased from 130 personSv in 1988 to 4.6 personSv at present. This reduction was attributed to: a decrease in the number of radioactive products (gas mantles), lower estimates of the number of radioactive products present in the Netherlands thanks to new information (camera lenses, smoke detectors containing Ra-226), replacement of radioactive by non-radioactive products (gas mantles, dental protheses), and a lowe...

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

Energies and media nr 28. Uranium mining exploitations and residues. Uranium mines in Niger. Depleted uranium as a by-product of enrichment

International Nuclear Information System (INIS)

2009-02-01

After some comments on recent events in the nuclear sector in different countries (USA, China, India, UK, Sweden, Italy and France), this publication addresses the issue of uranium mining exploitations and of their residues. It comments the radioactivity in mining areas, briefly discusses the issue of low doses, describes the uranium ore and its processing, indicates which are the various residues of the mining activity (sterile uncovered tailings, non exploitable mineralized rocks, ore and residue processing, residue radioactivity, mine closing down, witnesses on health in ancient mines). Some reflections are stated about uranium mines in Niger, and about depleted uranium as a by-product of the enrichment activity

Radioactivity distribution of the fruit trees ascribable to radioactive fall out. A study on stone fruits cultivated in low level radioactivity region

International Nuclear Information System (INIS)

Takata, Daisuke; Yasunaga, Eriko; Nakanishi, Tomoko M.; Sasaki, Haruto; Oshita, Seiichi; Tanoi, Keitaro

2012-01-01

After the accident of Fukushima Daiichi Nuclear Power Plant, radioactivity of fruit trees grown at an experimental farm of Nishi-Tokyo City in Tokyo, which was located about 230 km away from the power plant, was measured. Each organ of Japanese apricot and peach trees was taken at harvesting stage, respectively, and the radioactivity of 134 Cs and 137 Cs was measured. Although radioactivity of orchard soil and tree each organ were low generally, that of bark sampled from 3-old-year branch was as high as 1570 Bq/kg-dry weight. The total radioactivity of 134 Cs and 137 Cs in edible portion was far lower than that of the regulation level. (author)

Low-Dose Radioactive Iodine Destroys Thyroid Tissue Left after Surgery

Science.gov (United States)

A low dose of radioactive iodine given after surgery for thyroid cancer destroyed (ablated) residual thyroid tissue as effectively as a higher dose, with fewer side effects and less exposure to radiation, according to two randomized controlled trials.

Radioactivity in food crops

Energy Technology Data Exchange (ETDEWEB)

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

1983-05-01

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

Spanish high level radioactive waste management system issues

International Nuclear Information System (INIS)

Ulibarri, A.; Veganzones, A.

1993-01-01

The Empresa Nacional de Residuous Radiactivos, S.A. (ENRESA) was set up in 1984 as a state-owned limited liability company to be responsible for the management of all kinds of radioactive wastes in Spain. This paper provides an overview of the strategy and main lines of action stated in the third General Radioactive Waste Plan, currently in force, for the management of spent nuclear fuel and high-level wastes, as well as an outline of the main related projects, either being developed or foreseen. Aspects concerning the organizational structure, the economic and financing system and the international co-operational are also included

Predicting Induced Radioactivity at High Energy Accelerators

Energy Technology Data Exchange (ETDEWEB)

Fasso, Alberto

1999-08-27

Radioactive nuclides are produced at high-energy electron accelerators by different kinds of particle interactions with accelerator components and shielding structures. Radioactivity can also be induced in air, cooling fluids, soil and groundwater. The physical reactions involved include spallations due to the hadronic component of electromagnetic showers, photonuclear reactions by intermediate energy photons and low-energy neutron capture. Although the amount of induced radioactivity is less important than that of proton accelerators by about two orders of magnitude, reliable methods to predict induced radioactivity distributions are essential in order to assess the environmental impact of a facility and to plan its decommissioning. Conventional techniques used so far are reviewed, and a new integrated approach is presented, based on an extension of methods used at proton accelerators and on the unique capability of the FLUKA Monte Carlo code to handle the whole joint electromagnetic and hadronic cascade, scoring residual nuclei produced by all relevant particles. The radiation aspects related to the operation of superconducting RF cavities are also addressed.

The verification tests of residual radioactivity measurement and assessment techniques for buildings and soils

International Nuclear Information System (INIS)

Onozawa, T.; Ishikura, T.; Yoshimura, Yukio; Nakazawa, M.; Makino, S.; Urayama, K.; Kawasaki, S.

1996-01-01

According to the standard procedure for decommissioning a commercial nuclear power plant (CNPP) in Japan, controlled areas will be released for unrestricted use before the dismantling of a reactor building. If manual survey and sampling techniques were applied to measurement for unrestricted release on and in the extensive surface of the building, much time and much specialized labor would be required to assess the appropriateness of the releasing. Therefore the authors selected the following three techniques for demonstrating reliability and applicability of the techniques for CNPPs: (1) technique of assessing radioactive concentration distribution on the surface of buildings (ADB); (2) technique of assessing radioactive permeation distribution in the concrete structure of buildings (APB); (3) technique of assessing radioactive concentration distribution in soil (ADS). These tests include the techniques of measuring and assessing very low radioactive concentration distribution on the extensive surfaces of buildings and the soil surrounding of a plant with automatic devices. Technical investigation and preliminary study of the verification tests were started in 1990. In the study, preconditions were clarified for each technique and the performance requirements were set up. Moreover, simulation models have been constructed for several feasible measurement method to assess their performance in terms of both measurement test and simulation analysis. Fundamental tests have been under way using small-scale apparatuses since 1994

Evaluation of Total Nitrite Pattern Visualization as an Improved Method for Gunshot Residue Detection and its Application to Casework Samples.

Science.gov (United States)

Berger, Jason; Upton, Colin; Springer, Elyah

2018-04-23

Visualization of nitrite residues is essential in gunshot distance determination. Current protocols for the detection of nitrites include, among other tests, the Modified Griess Test (MGT). This method is limited as nitrite residues are unstable in the environment and limited to partially burned gunpowder. Previous research demonstrated the ability of alkaline hydrolysis to convert nitrates to nitrites, allowing visualization of unburned gunpowder particles using the MGT. This is referred to as Total Nitrite Pattern Visualization (TNV). TNV techniques were modified and a study conducted to streamline the procedure outlined in the literature to maximize the efficacy of the TNV in casework, while reducing the required time from 1 h to 5 min, and enhancing effectiveness on blood-soiled samples. The TNV method was found to provide significant improvement in the ability to detect significant nitrite residues, without sacrificing efficiency, that would allow for the determination of the muzzle-to-target distance. © 2018 American Academy of Forensic Sciences.

INFLUENCE OF RESIDUAL VARUS DEFORMITY ON CLINICAL, FUNCTIONAL, RADIOLOGICAL AND DYNAMOMETRIC OUTCOMES OF TOTAL KNEE ARTHROPLASTY

Directory of Open Access Journals (Sweden)

M. P. Zinoviev

2017-01-01

Full Text Available Purpose of the study – to evaluate the influence of residual varus deformity of the lower leg on clinical, functional and dynamometric outcomes of TKR.Material and methods. In the period from September 2014 till May 2015 951 total knee replacement surgeries were performed in Ural clinical and rehabilitation center in 933 patients with initial varus deformity of lower limb. However, in 52 cases (5.5% residual varus deformity of >3° persisted. The main group included 36 patients with mean residual varus deformity of lower leg of 3.9°±0.74° (from 3.1° to 5.6°, the control group included 34 patients with neutral mechanic axis of the lower leg. Evaluation of treatment outcomes was performed on average 14.2±1.8 months after the procedure using functional assessment of the patients according to KSS (Knee Society Score, subjective assessment of life quality (SF36, as well as evaluation of the static-dynamic function of the lower leg on diagnostic and treatment complex Biodex Systems 4 Quick Set and assessment of stability of components fixation by F.C. Ewald scale in modification of O.A. Kudinov et al.Results. Functional assessment of the patients according to KSS (Knee Society Score for the main group was 84.0±4.6, in control group – 82.2±4.1 points (p>0.05. Subjective assessment of life quality (SF36 in the main group was 162.6±6.4 points, in control group – 164.3±8.1 points (p>0.05. In terms of flexion and extension of lower leg there were no significant differences between two groups when assessing static and dynamic function by treatment and diagnostic complex «Biodex Systems 4 Quick Set» on average in 14.2±1.8 months after procedure: neither isometric nor isokinetic parameters in both groups demonstrated statistically significant differences (p>0.05. Based on X-rays evaluation there were no abnormalities in components fixation in both groups. There were no statistically significant differences identified in KSS and SF36 scales

Radioactivity in the Marine Environment. Chapter 1

International Nuclear Information System (INIS)

Zal U'yun Wan Mahmood; Abdul Kadir Ishak; Norfaizal Mohamad; Wo, Y.M.; Kamarudin Samuding

2015-01-01

Radionuclide (radioactive isotopes or radioisotopes is widely distributed on the ground primarily in marine environments. Nowadays, more than 340 isotopes has been identified exist in our earth especially in marine environment. From that total, 80 isotopes was radioactive. The existence of radioactivity in the marine environment is through the direct and indirect distribution of radionuclides

Monitoring dissolved radioactive cesium in Abukuma River in Fukushima Prefecture

International Nuclear Information System (INIS)

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

2013-01-01

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

Radioprotection and management of radioactive residues study in the radiopharmaceuticals laboratories

International Nuclear Information System (INIS)

Zidan, Priscila M.; Silva, Maria Isabel B. da

2002-01-01

The 123 I, used in the thyroid cancer diagnoses, is being used at several clinics of nuclear medicine, instead of 131 I. This last one, for presenting half-life 15 times bigger than the first one, causes larger doses to the patient and slower exams. Another subject is the management of the residues generated by radiopharmaceutical laboratories, which requests lager physical space, in the case of 131 I. In the present work, six radiopharmaceutical laboratories of the state of Rio de Janeiro were visited. All of them use the 131 I produced by the Nuclear Engineering Institute. In these visits radioprotection procedures and the management of residues of those laboratories were evaluated, as well as the available infrastructure

Evaluation of dried vegetables residues for poultry: II. Effects of feeding cabbage leaf residues on broiler performance, ileal digestibility and total tract nutrient digestibility.

Science.gov (United States)

Mustafa, A F; Baurhoo, B

2017-03-01

A study was conducted to investigate the effects of partial replacing corn and soybean meal with dried cabbage leaf residues (DCR) on broiler growth performance, apparent ileal nutrient digestibility, and apparent total tract nutrient utilization. Dietary treatments include 4 levels of DCR (0, 3, 6, and 9%). Two hundred and twenty-four day-old male broilers were randomly assigned to one of 4 groups (8 cage replicates; 7 birds/cage) and grown over a 35-d experimental period. Results showed that feeding DCR had no effects on daily body weigh gain (average 53.4 g/d), daily feed intake (average 94.9 g/d), and feed conversion ratio (average 1.78 g of feed/g of gain). Inclusion of DCR reduced apparent ileal DM (quadratic effect, P digestibility of younger birds (d 21) while incremental levels of DCR had no effect on apparent ileal nutrient digestibilities of older birds (d 35). Apparent total tract digestibility of DM, OM, and CP increased (linear effect, P digestibility of older birds and improved apparent total tract nutrient digestibility. © 2016 Poultry Science Association Inc.

Control criteria for residual contamination in materials considered for recycle and reuse

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Hill, R.L.; Aaberg, R.L.

1993-11-01

Pacific Northwest Laboratory (PNL) is collecting data and conducting technical analyses to support the US Department of Energy (DOE), Office of Environmental Guidance, Air, Water, and Radiation Division (DOE/EH-232) in determining the feasibility of developing radiological control criteria for recycling or reuse of metals or equipment containing residual radioactive contamination from DOE operations. The criteria, framed as acceptable concentrations for release of materials for recycling or reuse, will be risk-based and will be developed through analysis of radiation exposure scenarios and pathways. The analysis will include evaluation of relevant radionuclides, potential mechanisms of exposure, and non-health-related impacts of residual radioactivity on electronics and film. The analyses will consider 42 key radionuclides that are generated during DOE operations and may be contained in recycled or reused metals or equipment

National Plan for the management of radioactive materials and wastes 2013-2015

International Nuclear Information System (INIS)

2013-02-01

This new release of the National Plan for the management of radioactive materials and wastes (PNGMDR) first addresses the principles and objectives of this management: presentation of radioactive materials and wastes, principles to be taken into account to define the different management ways, legal and institutional framework for waste management, societal dimension and memory safeguarding, waste management cost and financing. It proposes an assessment and draws perspectives for the existing management practices: management of historical situations, management of residues of mine processing and mine tailings, management of radioactive wastes, waste management with respect to radioactive decay, valorization of radioactive wastes, incineration of radioactive wastes, storage of very-low-activity wastes, of storage of low- and medium-activity and short-life wastes, management of reinforced natural radioactivity wastes. The third part gives an overview of needs and perspectives for management methods: wastes requiring a specific processing, low-activity long-life wastes, and high-activity and medium-activity long-life wastes

Radioactivity of the JINR site environment

International Nuclear Information System (INIS)

Alenitskaya, S.I.; Bamblevskij, V.P.; Kargin, A.N.; Komochkov, M.M.

1977-01-01

The results of the study of the existing levels of enviromental radioactivity in the JINR region for 1971-1975; content of radioactive products in the grass and surface soil layer, levels of the total alpha - and beta-radioactivity of water of open reservoirs as well as the background of the gamma-radiation and charged particles are presented. The study testifies, that the operation of the JINR nuclear-physical installations does not significantly affect the radioactivity of the environment which is mainly conditioned by the products of the natural origin and the global fallouts

Thallium-201 for cardiac stress tests: residual radioactivity worries patients and security.

Science.gov (United States)

Geraci, Matthew J; Brown, Norman; Murray, David

2012-12-01

A 47-year-old man presented to the Emergency Department (ED) in duress and stated he was "highly radioactive." There were no reports of nuclear disasters, spills, or mishaps in the local area. This report discusses the potential for thallium-201 (Tl-201) patients to activate passive radiation alarms days to weeks after nuclear stress tests, even while shielded inside industrial vehicles away from sensors. Characteristics of Tl-201, as used for medical imaging, are described. This patient was twice detained by Homeland Security Agents and searched after he activated radiation detectors at a seaport security checkpoint. Security agents deemed him not to be a threat, but they expressed concern regarding his health and level of personal radioactivity. The patient was subsequently barred from his job and sent to the hospital. Tl-201 is a widely used radioisotope for medical imaging. The radioactive half-life of Tl-201 is 73.1h, however, reported periods of extended personal radiation have been seen as far out as 61 days post-administration. This case describes an anxious, but otherwise asymptomatic patient presenting to the ED with detection of low-level personal radiation. Documentation should be provided to and carried by individuals receiving radionuclides for a minimum of five to six half-lives of the longest-lasting isotope provided. Patients receiving Tl-201 should understand the potential for security issues; reducing probable tense moments, confusion, and anxiety to themselves, their employers, security officials, and ED staff. Copyright © 2012 Elsevier Inc. All rights reserved.

Bituminization of liquid radioactive waste. Part 3

International Nuclear Information System (INIS)

G'oshev, G.S.; Gradev, G.D.; Stefanova, I.G.; Milusheva, A.G.; Guteva, E.S.; Stefanov, G.I.

1991-01-01

The elaborated technology for bituminization of liquid radioactive wastes (salt concentrates) is characterized by the fact that the bituminization process takes place in two stages: concentration of the liquid residue and evaporation of the water with simultaneous homogeneous incorporation of the salts in the melted bitumen. An experimental installation for bituminization of salt concentrates was designed on the basis of this technology. The experience accumulated during the design and construction of the installation for bituminization of salt concentrates could be used for designing and constructing an industrial installation for bituminization of the liquid residue of the nuclear power plants. 2 tabs., 3 figs., 3 refs

Radioactive substances detection at solid waste incinerators entrance

International Nuclear Information System (INIS)

Bourjat, V.; Carre, J.; Perrier-Rosset, A.

2001-01-01

SYCTOM'S incinerators, operated by TIRU will soon be fitted out with radioactivity control systems to prevent entrance of radioactive waste. Such implementation aims at reducing health risks due to exposition of operators working in incinerators or in sites receiving incineration residues. Radioactive wastes are supposed to be well managed: in the case where the radioactive elements period is short, they have to be stored for a precise time; in all the other cases, a statutory organism dealing with radioactive waste (ANDRA) has to take charge of them. Meanwhile they may arrived in incinerators by mistake. It's difficult to regulate radioactivity control systems for technical reasons; the measured values can be really different from these in the truck because of radiation decreasing; moreover it can't be correlated to an activity, hence it can't be compared to exemption values or to the limits that characterise a radioactive substance. It can explain why regulated documents don't indicate the way to fix alarm threshold. Implementing such a system is not sufficient: when the alarm sound, the following steps can be applied: checking the missing of interference, potential truck return to sender, putting the truck in quarantine, information of authorities and main actors, calling on a specialize company to locate, extract and package the radiation source, storage of this source and spectrometric analysis to identify and quantify the radioactive elements in order to determinate its way of elimination. (authors)

Analysis and radiological assessment of residues containing NORM materials resulting from earlier activities including modelling of typical industrial residues. Pt. 1. Historical investigation of the radiological relevance of NORM residues and concepts for site identification

International Nuclear Information System (INIS)

Reichelt, Andreas; Niedermayer, Matthias; Sitte, Beate; Hamel, Peter Michael

2007-01-01

Natural radionuclides are part of the human environment and of the raw materials used. Technical processes may cause their accumulation in residues, and the result will be so-called NORM materials (Naturally occurring radioactive material). The amended Radiation Protection Ordinance (StrlSchV 2001) specifies how the public should be protected, but there are also residues dating back before the issuing of the StrlSchV 2001, the so-called NORM residues. The project intended to assess the risks resulting from these residues. It comprises four parts. Part 1 was for clarification of the radiological relevance of NORM residues and for the development of concepts to detect them. The criterion for their radiological relevance was their activity per mass unit and the material volume accumulated through the centuries. The former was calculated from a wide bibliographic search in the relevant literature on radiation protection, while the mass volume was obtained by a detailed historical search of the consumption of materials that may leave NORM residues. These are, in particular, residues from coal and ore mining and processing. To identify concrete sites, relevant data sources were identified, and a concept for identification of concrete NORM residues was developed on this basis. (orig.) [de

Radioactivity of neutron-irradiated cat's-eye chrysoberyls

Energy Technology Data Exchange (ETDEWEB)

Tang, S.M. E-mail: phytsm@leonis.nus.edu.sg; Tay, T.S

1999-04-02

The recent report of marketing of radioactive chrysoberyl cat's-eyes in South-East Asian markets has led us to use an indirect method to estimate the threat to health these color-enhanced gemstones may pose if worn close to skin. We determined the impurity content of several cat's-eye chrysoberyls from Indian States of Orissa and Kerala using PIXE, and calculated the radioactivity that would be generated from these impurities and the constitutional elements if a chrysoberyl was irradiated by neutrons in a nuclear reactor for color enhancement. Of all the radioactive nuclides that could be created by neutron irradiation, only four ({sup 46}Sc, {sup 51}Cr, {sup 54}Mn and {sup 59}Fe) would not have cooled down within a month after irradiation to the internationally accepted level of specific residual radioactivity of 2 nCi/g. The radioactivity of {sup 46}Sc, {sup 51}Cr and {sup 59}Fe would only fall to this safe limit after 15 months and that of {sup 54}Mn could remain above this limit for several years.

Experimental studies of applicability of the wet air oxidation for purification liquid radioactive waste

International Nuclear Information System (INIS)

Sergienko, V. I.; Dobrzansky, V. G.

2005-01-01

The scheme of handling with liquid radioactive waste (LRW) accepted to exploitation at atomic electric station (AWS) is often connected with evaporating technologies. In this case vat residues of evaporating systems with activity 10 5 -10 6 Bq/1 and containing to 200-300 g/1 of salts are delivered up to LRW storages for lasting keeping. This schema does not correlate to the modern safety standards of handling with LRW, therefore at present numerous works are being carried on including those using technology of accumulated vat residues processing. Some successful experiments on sorption purification of high-salt LRW from cesium radionuclides giving the principal contribution into the total activity of a certain LRW are known. Unfortunately, attempts of sorption purification of the vat residues from other long-lived radionuclides (mainly from 60 Co-radionuclide) were unsuccessful up to the present time. It is found with the fact that the vat residues contain a considerable amount of complexing agent producing stable complexes with transition metal radionuclides including those of 60 Co. Extreme oxidation of the vat residues for decomposition of radioactive organic complexes is one of the solutions of this problem. The works related to oxidation of LRW including the AES vat residues with ozone, hydrogen peroxide as well as photo catalytic and electrochemical oxidation are known, however, possibilities of wet air oxidation (WAO) for LRW processing are not studied till the present time. Condition for decomposition of cobalt complex compounds and necessary excess of oxidizing agent may be easily attained with WAO usage. The necessary experiments were carried out at the experimental plant with the great interface surface (oxygen-solutions) equal to 400m -1 and 3 mm probe bed thickness. The heating time of the reactor to the working temperature 250 .deg. C did not exceed 50 seconds. 20... 50-fold oxidizer excess was achieved by the initial oxygen pressure into the reactor

Inventory of radioactive material entering the marine environment: Sea disposal of radioactive waste

International Nuclear Information System (INIS)

1991-03-01

Variable amounts of packaged low level radioactive waste have been disposed at more than 50 sites in the northern parts of the Atlantic and Pacific Oceans. The last known disposal operation was in 1982, at a site about 550 km off the European continental shelf in the Atlantic Ocean. Since 1957, the IAEA has provided specific guidance and recommendations for ensuring that disposal of radioactive wastes into the sea will not result in unacceptable hazards to human health and marine organisms, damage to amenities or interference with other legitimate uses of the sea. In 1972, the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter designated the IAEA as the competent international authority in matters related to sea disposal of radioactive waste. The Contracting Parties requested the IAEA to develop an inventory of radioactive wastes entering the marine environment from all sources as an information base with which the impact of radioactive materials from disposal operations can be more adequately assessed. The continuous compilation of these data could ensure that the IAEA recommendations on the disposal rate in a single basin are not overstepped. The inventory shows that between 1946 to 1982 an estimated 46 PBq 1 (1.24 MCi) of radioactive waste coming from research, medicine, the nuclear industry and military activities were packaged, usually in metal drums lined with a concrete or bitumen matrix, and disposed of at sea. This inventory includes some unpackaged wastes and liquid wastes which were disposed of from 1950 to 1960. Beta-gamma emitters represent more than 98% of the total radioactivity of the waste and tritium alone represents one third of the total radioactivity disposed at the North East Atlantic sites. The other beta-gamma emitters radionuclides include 90 Sr, 137 Cs, 55 Fe, 58 Co, 60 Co, 125 I and 14 C. The wastes also contain low quantities of alpha-emitting nuclides with plutonium and americium isotopes representing

Residual radioactivity investigation and radiological assessments for self-disposal of concrete waste in nuclear fuel processing facility

International Nuclear Information System (INIS)

Seol, Jeung Gun; Ryu, Jae Bong; Cho, Suk Ju; Yoo, Sung Hyun; Song, Jung Ho; Baek, Hoon; Kim, Seong Hwan; Shin, Jin Seong; Park, Hyun Kyoun

2007-01-01

In this study, domestic regulatory requirement was investigated for self-disposal of concrete waste from nuclear fuel processing facility. And after self-disposal as landfill or recycling/reuse, the exposure dose was evaluated by RESRAD Ver. 6.3 and RESRAD BUILD Ver. 3.3 computing code for radiological assessments of the general public. Derived clearance level by the result of assessments for the exposure dose of the general public is 0.1071Bq/g (3.5% enriched uranium) for landfill and 0.05515 Bq/cm 2 (5% enriched uranium) for recycling/reuse respectively. Also, residual radioactivity of concrete waste after decontamination was investigated in this study. The result of surface activity is 0.01Bq/cm 2 for emitter and the result of radionuclide analysis for taken concrete samples from surface of concrete waste is 0.0297Bq/g for concentration of 238 U, below 2w/o for enrichment of 235 U and 0.0089Bq/g for artificial contamination of 238 U respectively. Therefore, radiological hazard of concrete waste by self-disposal as landfill and recycling/reuse is below clearance level to comply with clearance criterion provided for Notice No. 2001-30 of the MOST and Korea Atomic Energy Act

Radioactive facilities classification criteria

International Nuclear Information System (INIS)

Briso C, H.A.; Riesle W, J.

1992-01-01

Appropriate classification of radioactive facilities into groups of comparable risk constitutes one of the problems faced by most Regulatory Bodies. Regarding the radiological risk, the main facts to be considered are the radioactive inventory and the processes to which these radionuclides are subjected. Normally, operations are ruled by strict safety procedures. Thus, the total activity of the radionuclides existing in a given facility is the varying feature that defines its risk. In order to rely on a quantitative criterion and, considering that the Annual Limits of Intake are widely accepted references, an index based on these limits, to support decisions related to radioactive facilities, is proposed. (author)

Cementitious Composites for Immobilization of Radioactive Waste into Final Wasteform

International Nuclear Information System (INIS)

Varlakov, A.P.

2013-01-01

Research and development works are important on universal cementation technological processes to achieve maximal conditioning efficiency for various type wastes such as saline liquid radioactive waste (LRW), where the variants of cement composition formulations, modes of cement compounds preparation and types of equipment are minimised. This work presents the results of development of multi-component cement compositions for the complex of technological processes of different types of radioactive waste (RAW) cementation: concentrated saline LRW, concentrated boron-containing saline LRW, LRW with high surface active substances content, with residues, liquid organic radioactive waste, spent ion-exchange resins and filter-perlite powder, ash residues from solid radioactive waste (SRW) combustion, mixed closely packed and large-fragmented SRW. The research has found technological parameters of equipment and cement compositions providing reliable RAW cementation. Continuous and periodic cycle plants were developed for LRW cementation by mixing. Pouring and penetration methods were developed for SRW cementation. Based on compliance with equipment parameters, methods and cement grouts were selected for most effective technological processes of cementation. Formulations of cement compositions were developed to provide reliable preparation of cement compounds with maximal waste loading at required cement compound quality. The complex of technological processes of cementation using multi-component cement compositions allows highly efficient treatment of the wide range of RAW including problematic waste streams and wastes generated in small amounts. Rational reduction of cementation variants significantly increases economical efficiency of immobilisation. (author)

Evaluation on radioactive level and quality of aquatic environment in Suzhou

International Nuclear Information System (INIS)

Yu Rongsheng; Tu Yu; Zhang Ruiju

2007-01-01

Objective: To assess the quality grade of water source in Suzhou in terms of the radioactive level. Methods: The levels of total α and total β activities in samples of water were detected by relative measurement with medium thickness using model BH 1216 low level α and β detector. 241 Am and pure potassium chloride were used as reference radioactive sources. Results: Among all samples collected, the measured levels varied from (2.62 ± 0.17) x 10 -2 to (8.48±2.80) x 10 -2 Bq/L for total α and (0.77 ± 0.47) x 10 -1 to (3.75 ± 0.26) x 10 -1 Bq/L for total β, the average levels of β/α were from 1.6 to 7.2. Conclusions: The radioactivity level of water source in Suzhou was within the natural background range, free from contamination of artificial radioactive nuclides, which was regarded as good in quality in terms of radioactive level. It is shown that the radioactivity of well water was highest among all investigated water sources. (authors)

Disposal options for radioactive residues. Development of interdisciplinary evaluation principles in ENTRIA; Entsorgungsoptionen fuer hoch radioaktive Abfaelle. Die Schaffung interdisziplinaerer Bewertungsgrundlagen in ENTRIA

Energy Technology Data Exchange (ETDEWEB)

Walther, C. [Hannover Univ. (Germany). Inst. fuer Radiooekologie und Strahlenschutz; Chaudry, S.; Plischke, E.; Roehlig, K.J. [TU Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Endlagerforschung; Hocke, P. [Karlsruher Institut fuer Technologie, Karlsruhe (Germany). Inst. fuer Technikfolgenabschaetzung und Systemanalyse; Eckhardt, A. [risicare GmbH, Zollikerberg (Switzerland); Ott, K. [Kiel Univ. (Germany). Philosophisches Seminar

2016-07-01

ENTRIA, short for ''Disposal Options for Radioactive Residues: Interdisciplinary Analyses and Development of Evaluation Principles'', is a joint project of twelve institutes or departments of German universities and research institutions as well as a partner from Switzerland. The fundamentally new approach here is the plurality of represented disciplines. ENTRIA analyzes radioactive waste management subjects from the viewpoint of natural sciences, engineering, arts, law and social science. ENTRIA works independently from politics, operators und interest groups. ENTRIA performs purely scientific research analyzing the three most important radioactive waste management option:''Final disposal in deep geological formations without any arrangements for retrieval (maintenance-free deep geological disposal)'', ''disposal in deep geological formations with arrangements for monitoring and retrieval'' and ''surface storage''. Based on these options ENTRIA developed generic ''reference models'' and generic host-rockdependent container models (ENCON). All these models are of generic character, but are elaborated to an extent, e.g. with respect to reversibility time scales, as is necessary for a comparative differentiated evaluation. Long-term surface storage is considered and evaluated because of the increasingly apparent need to address interim storage not only as (temporary) alternative, but also as a necessary part of the overall process. Besides disciplinary work packages performed in ENTRIA several tasks combine the expertise and perspective of disciplines which could classically be considered ''far apart''. A key task is the creation of interdisciplinary evaluation principles. This article provides insight into interdisciplinary working within ENTERIA and describes the present status of this work from the perspective of the authors. However, this is not

Radioactive content in aerosols and rainwater

International Nuclear Information System (INIS)

Rodriguez Perestelo, N.; Lopez Perez, M.; Rodriguez, S.; Duarte, X.; Catalan, A.; Fernandez de Aldecoa, J. C.; Hernandez, J.

2013-01-01

The environmental radiological characterization of a place requires knowledge of the radioactive contents of its components, such as air (aerosol), rain, soil, etc ... Inhalation of radioactive aerosols in the air remains the main component of the total dose to the world population. This work focuses on its determination. (Author)

Psychological and social aspects verified after the Goiania's radioactive accident

International Nuclear Information System (INIS)

Helou, Suzana

1995-01-01

Psychological and social aspects verified after the radioactive accident occurred in 1987 in Goiania - brazilian city - are discussed. With this goal was going presented a public opinion research in order to retract the Goiania's radioactive accident residual psychological effects. They were going consolidated data obtained in 1.126 interviews. Four involvement different levels groups with the accident are compared with regard to the event. The research allowed to conclude that the accident affected psychologically somehow all Goiania's population. Besides, the research allowed to analyze the professionals performance quality standard in terms of the accident

Hungarian situation of the technologically enhanced naturally occuring radioactive materials

International Nuclear Information System (INIS)

Juhasz, L.; Szerbin, P.; Czoch, I.

2003-01-01

Full text: In Hungary, the main goal is that the Hungarian regulations should meet with the EU Directive No. 96/29. For this aim, a surveying project has been launched in order to collect all relevant information about the Hungarian TENORM situation. This surveying programme covers a lot of data collection (work activities, disposal places, residue quantities) and radiological measurements on the TENORM site. The Hungarian situation of TENORM definitely differs from other countries in the aspect of occurrence forms of natural sources (or in the imported raw materials), in the quantities of exploitation, in the level of the radioactivity and in the applied technological processes. Firstly, those work activities have been choosen where the huge amount of residues have been produced. The other criteria is that the activity concentration in a great portion of the given residues is much higher than the average activity concentration of the typical Hungarian soil. After filtering and ranking, the following main activities enhanced the radioactivity level are left: uranium mining and milling, coal mining, coal firing in power plants, bauxite mining and aluminous earth production. At the uranium mining and milling area the uranium content of residues ranges from 20 to 70 g t -1 , and above those the dose rate is 0.4-10 μSv h -1 . The waste rock piles and heaps for leaching were restored and the remediation of tailings ponds is still under way. In the mountain Mecsek and on the territory from the highland Balaton to the mountain Vertes, the radioactivity level of the coals is 10-50 times higher than the worldwide average. The coal fired plants have piled up in the order of magnitude of 10 million tons of fly ash, bottom ash and slag in ponds around the plants. The radioactivity of U-238 series of ash and slag is in the range from 200 to 2000 Bq·kg -1 . The radionuclide concentrations of bauxite ores range from 200 to 300 Bq·kg -1 . At the refining factories, a lot of red

Method for storing radioactive rare gases

International Nuclear Information System (INIS)

Watabe, Atsushi; Nagao, Hiroyuki; Takiguchi, Yukio; Kanazawa, Toshio; Soya, Masataka.

1975-01-01

Object: To safely and securely store radioactive rare gases for a long period of time. Structure: The waste gases produced in nuclear power plant are cooled by a cooler and then introduced into a low temperature adsorbing device so that the gases are adsorbed by adsorbents, and then discharged into atmosphere through the purifying gas discharge line. When the radioactive rare gases reach a level of saturation in the amount of adsorption, they are heated and extracted by a suction pump and heated by a heater. The gases are then introduced into an oxygen-impurity removing device and the purified rare gases containing no oxygen and impurities are cooled by a cooler and fed into a gas holder. When the amount of radioactive rare gases stored within the gas holder reaches a given level, they are compressed and sealed by a compressure into a storing cylinder and residual gases in the piping are sucked and recovered into the gas holder, after which the cylinder is removed and stored in a fixed room. (Kamimura, M.)

Method and device for solidifying radioactive waste

International Nuclear Information System (INIS)

Hayashi, Tadamasa.

1981-01-01

Purpose: To solidify radioactive waste without producing radioactive dusts by always heating and evaporating the water from liquid radioactive waste in a mixture of liquid plastic and exhausting the molten mixture of the waste residue and the plastic material. Constitution: Liquid plastic material in a tank cooled to prevent polymerization or changes of its properties is continuously supplied to the top of a heating and mixing evaporator by a constant supply pump. After the heat transfer surface of the evaporator is covered with the plastic material, radioactive waste in the tank is supplied to the evaporator via the constant supply pump. The waste is abruptly mixed with the plastic material by an agitating rotor, heated by a heater, and the evaporated water is fed to a condenser. An anhydrous molten mixture is continuously exhausted from the bottom of the evaporator into a mixture cooler, a polymerizing agent and catalyst are introduced thereinto from a polymerizing agent tank and a catalyst tank, inhibitor is introduced thereinto from a polymerization inhibitor tank as required, and is filled with the mixture a solidifying container while it is cooled for its polymerization and solidification. (Yoshino, Y.)

Analysis of the total system life cycle cost for the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

1989-05-01

The total-system life-cycle cost (TSLCC) analysis for the Department of Energy's (DOE) Civilian Radioactive Waste Management Program is an ongoing activity that helps determine whether the revenue-producing mechanism established by the Nuclear Waste Policy Act of 1982 -- a fee levied on electricity generated in commercial nuclear power plants -- is sufficient to cover the cost of the program. This report provides cost estimates for the sixth annual evaluation of the adequacy of the fee and is consistent with the program strategy and plans contained in the DOE's Draft 1988 Mission Plan Amendment. The total-system cost for the system with a repository at Yucca Mountain, Nevada, a facility for monitored retrievable storage (MRS), and a transportation system is estimated at $24 billion (expressed in constant 1988 dollars). In the event that a second repository is required and is authorized by the Congress, the total-system cost is estimated at $31 to $33 billion, depending on the quantity of spent fuel to be disposed of. The $7 billion cost savings for the single-repository system in comparison with the two-repository system is due to the elimination of $3 billion for second-repository development and $7 billion for the second-repository facility. These savings are offset by $2 billion in additional costs at the first repository and $1 billion in combined higher costs for the MRS facility and transportation. 55 refs., 2 figs., 24 tabs

Transporting large volumes of residual radioactive material: FUSRAP solutions

International Nuclear Information System (INIS)

Pressnell, T.; McDaniel, P.; Darby, J.

1997-01-01

During the 1940s, 1950s and 1960s, many sites in the United States were used by the Manhattan Engineer District and the Atomic Energy Commission for processing and storing uranium and thorium ores and metals. Some of the sites were owned by the federal government; others were owned by universities or other institutions; and still others, such as chemical plants, were privately owned. The Formerly Utilized Sites Remedial Action Program (FUSRAP) is one of several U.S. Department of Energy programs created to address radioactive contamination in excess of guidelines at these sites. FUSRAP currently includes 46 sites in 14 states. This article includes the following topics in describing FUSRAP work: Logistics challenges; engineering challenges (package inspection, equipment compatability, moisture content requirements, waste volume estimation); Traffic management

Analysis of spatial distribution and inventory of radioactivity within the uranium mill tailings impoundment

Directory of Open Access Journals (Sweden)

D. O. Bugai

2015-10-01

Full Text Available Results are presented of the characterization of radioactivity inventory of Zapadnoe uranium mill tailings impoundment situated at Pridneprovsky Chemical Plant (PChP; Dneprodzerzhinsk, Ukraine. Analyses of radioactivity data set based on analytical studies of core material from 15 characterization boreholes allowed significantly refining waste volume and radioactivity inventory estimates. Geostatistical analyses using variogram function have established that radioactivity distribution in Zapadnoe tailings is characterized by regular spatial correlation patterns. Ordinary kriging method was applied to assess distribution of radioactivity in 3D. Results of statistical analyses suggest significant redistribution of uranium in the dissolved form in the residues (presumably due to water infiltration process. The developed structural model for radioactivity distribution is used for further risk assessment analyses. Derived radioactivity correlation scales can be used for optimization of sample collection when characterizing the PChP Site and similar contaminated sites elsewhere.

What to do with radioactive wastes?

International Nuclear Information System (INIS)

2006-01-01

This power point presentation (82 slides) gives information on what is a radioactive waste, radioactivity and historical review of radioactivity, radioactive period, natural radioactivity (with examples of data), the three main radiation types (α, β, γ), the origin of radioactive wastes (nuclear power, research, defense, other), the proportion of radioactive wastes in the total of industrial wastes in France, the classification of nuclear wastes according to their activity and period, the quantities and their storage means, the 1991 december 30 law (France) related to the radioactive waste management, the situation in other countries (Germany, Belgium, Canada, USA, Finland, Japan, Netherlands, Sweden, Switzerland), volume figures and previsions for the various waste types in 2004, 2010 and 2020, the storage perspectives, the French national debate on radioactive waste management and the objective of perpetuated solutions, the enhancement of the public information, the 15 June 2006 law on a sustainable management of radioactive materials and wastes with three main axis (deep separation and transmutation, deep storage, waste conditioning and long term surface storage), and the development of a nuclear safety and waste culture that could be extended to other types of industry

Fate of 2,4-D Residues in Turkish Soil-Plant Ecosystems

International Nuclear Information System (INIS)

Önal, Q.; Gözek, K.

1981-01-01

Full text: 2,4-D is the most frequently used herbicide in Turkish agriculture especially in Middle Anatolia. Studies on the behaviour of 2,4-D in the soil-plant ecosystem is being carried out under laboratory and field conditions. Some preliminary results are reported. After four weeks, recovery of radioactivity in carbon dioxide, aceton extract and bound residue was averaged for various soils: 20%, 15% and 48%, respectively. Barley, wheat and oat grown for four weeks on 2,4-D contaminated soil, contained from 0,6 up to 8% of the radioactivity applied. (author)

Total hip arthroplasty performed in patients with residual poliomyelitis: does it work?

Science.gov (United States)

Yoon, Byung-Ho; Lee, Young-Kyun; Yoo, Jeong Joon; Kim, Hee Joong; Koo, Kyung-Hoi

2014-03-01

Patients with residual poliomyelitis can have advanced degenerative arthritis of the hip in the paralytic limb or the nonparalytic contralateral limb. Although THA is a treatment option for some of these patients, there are few studies regarding THA in this patient population. We therefore reviewed a group of patients with residual poliomyelitis who underwent cementless THA on either their paralytic limb or nonparalytic limb to assess (1) Harris hip scores, (2) radiographic results, including implant loosening, (3) complications, including dislocation, and (4) limb length discrepancy after recovery from surgery. From January 2000 to December 2009, 10 patients with residual poliomyelitis (10 hips, four paralytic limbs and six nonparalytic contralateral limbs) underwent THA using cementless prostheses. Harris hip scores, complications, and leg length discrepancy were determined by chart review, and confirmed by questionnaire and examination; radiographs were reviewed by two observers for this study. Followup was available for all 10 patients at a minimum of 3 years (median, 7 years; range, 3.4-13 years). Surgery was done at the same side of the paralytic limb in four hips and contralateral to the paralytic limb in six. All patients had pain relief and improvement in function; the Harris hip score improved from mean of 68 preoperatively to 92 at last followup (p = 0.043). However, only three patients had complete pain relief. One hip dislocated, which was treated successfully with closed reduction and a hip spica cast for 2 months. There was no loosening or osteolysis in this series. Leg length discrepancy improved after the index operation, but only in the THAs performed in the paralytic limbs. Cementless THA may be suitable for painful hips in adult patients with residual poliomyelitis. Nonetheless, these patients should be informed of the possibility of mild residual pain and persistent leg length discrepancy, particularly patients whose THA is performed on the

Persistence of malathion residues in stored milled rice: Direct and indirect applications

International Nuclear Information System (INIS)

Arshad, J.H.

1990-01-01

Two experiments were carried out: (i) to study the persistence of malathion residues in stored milled rice following multiple applications of 14 C-malathion to the bagged rice and (ii) to determine the degradation of malathion in stored milled rice and stored paddy following direct and single application of 14 C-malathion. The storage conditions were similar to those found in the local rice godowns. Three applications of malathion to the bagged milled rice resulted in the accumulation of malathion and its metabolites in and/or on the rice grains over the storage period. After 9 months' storage, ca. 4% of the total applied radioactivity, which amounted to 10 μg/g equivalent of 14 C residues, were found in and/or on the grains. About one fourth of the residue remained as the unchanged parent compound. On the other hand, when 14 C-malathion at the 10 ppm level was mixed directly with the milled rice or paddy prior to storage, the amount of malathion (recovered in the chloroform extracts) decreased from 6.2 μg/g at zero time to 2.9 μg/g after 3 months' storage for the milled rice samples. The major metabolite in the milled rice and paddy samples was malathion monocarboxylic acid with trace amounts of malathion dicarboxylic acid and malaoxon. (author). 5 refs, 3 tabs

Determination of radioactivity in Cisadane River

International Nuclear Information System (INIS)

Tarigan, C.; Lubis, E.

1993-01-01

Determination of radioactivity in Cisadane river. The determination of radioactivity in water and sediment samples from Cisadane river in the period of March 1989 through March 1990 has been carried out. The aim of the study is to get some information on the radionuclides species and its quantities in water and sediment samples. Sampling was done at randon from 12 stations of 5 km apart. Result of the determination showed that the average total α activity in water was 18.10 ± 13.26 mBq/l and in sediment 34.96 ± 9.99 Bq/kg. Total β activities in water was 129.95 ± 148.14 mBq/l and in sediment 275.94 ± 41.63 Bq/kg. Activities of K-40 and Ra-226 in water was 6.39 ± 2.16 Bq/l and 7.34 ± 1.61 Bq/l and in sediment 6.58 ± 1.80 Bq/kg for Ra-226 and 84.87 ± 16.55 Bq/kg for K-40. Compared to environmental quality standard data for water group A total α and β activities showed good quality river water. Compared to data from UNSCEAR, for similar sample the radioactivity level in Cisadane river was normal. This result gave an indication that total α and β radioactivities in the water and sediment are due to natural radionuclides. (authors). 6 refs., 8 tabs., 9 figs

Naturally Occurring Radioactive Materials in Uranium-Rich Coals and Associated Coal Combustion Residues from China.

Science.gov (United States)

Lauer, Nancy; Vengosh, Avner; Dai, Shifeng

2017-11-21

Most coals in China have uranium concentrations up to 3 ppm, yet several coal deposits are known to be enriched in uranium. Naturally occurring radioactive materials (NORM) in these U-rich coals and associated coal combustion residues (CCRs) have not been well characterized. Here we measure NORM (Th, U, 228 Ra, 226 Ra, and 210 Pb) in coals from eight U-rich coal deposits in China and the associated CCRs from one of these deposits. We compared NORM in these U-rich coals and associated CCRs to CCRs collected from the Beijing area and natural loess sediments from northeastern China. We found elevated U concentrations (up to 476 ppm) that correspond to low 232 Th/ 238 U and 228 Ra/ 226 Ra activity ratios (≪1) in the coal samples. 226 Ra and 228 Ra activities correlate with 238 U and 232 Th activities, respectively, and 226 Ra activities correlate well with 210 Pb activities across all coal samples. We used measured NORM activities and ash yields in coals to model the activities of CCRs from all U-rich coals analyzed in this study. The activities of measured and modeled CCRs derived from U-rich coals exceed the standards for radiation in building materials, particularly for CCRs originating from coals with U > 10 ppm. Since beneficial use of high-U Chinese CCRs in building materials is not a suitable option, careful consideration needs to be taken to limit potential air and water contamination upon disposal of U- and Ra-rich CCRs.

Determination of potassium concentration in salt water for residual beta radioactivity measurements

International Nuclear Information System (INIS)

Suarez-Navarro, J.A.; Pujol, Ll.

2004-01-01

High interferences may arise in the determination of potassium concentration in salt water. Several analytical methods were studied to determine which method provided the most accurate measurements of potassium concentration. This study is relevant for radiation protection because the exact amount of potassium in water samples must be known for determinations of residual beta activity concentration. The fitting algorithm of the calibration curve and estimation of uncertainty in potassium determinations were also studied. The reproducibility of the proposed analytical method was tested by internal and external validation. Furthermore, the residual beta activity concentration of several Spanish seawater and brackish river water samples was determined using the proposed method

Acid digestion of combustible radioactive wastes

International Nuclear Information System (INIS)

Allen, C.R.; Lerch, R.E.; Crippen, M.D.; Cowan, R.G.

1982-03-01

The following conclusions resulted from operation of Radioactive Acid Digestion Test Unit (RADTU) for processing transuranic waste: (1) the acid digestion process can be safely and efficiently operated for radioactive waste treatment.; (2) in transuranic waste treatment, there was no detectable radionuclide carryover into the exhaust off-gas. The plutonium decontamination factor (DF) between the digester and the second off-gas tower was >1.5 x 10 6 and the overall DF from the digester to the off-gas stack was >1 x 10 8 ; (3) plutonium can be easily leached from undried digestion residue with dilute nitric acid (>99% recovery). Leachability is significantly reduced if the residue is dried (>450 0 stack temp.) prior to leaching; (4) sulfuric acid recovery and recycle in the process is 100%; (5) nitric acid recovery is typically 35% to 40%. Losses are due to the formation of free nitrogen (N 2 ) during digestion, reaction with chlorides in waste (NO 2 stack was > 1.5 x 10 6 andl), and other process losses; (6) noncombustible components comprised approximately 6% by volume of glovebox waste and contained 18% of the plutonium; (7) the acid digestion process can effectively handle a wide variety of waste forms. Some design changes are desirable in the head end to reduce manual labor, particularly if large quantities of specific waste forms will be processed; (8) with the exception of residue removal and drying equipment, all systems performed satisfactorily and only minor design and equipment changes would be recommended to improve performance; and(9) the RADTU program met all of its planned primary objectives and all but one of additional secondary objectives

Measuring radioactivity in the body

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-09-15

Techniques of measuring the total amount of radioactivity in the body of a living person as well as the principal applications of such measurements were reviewed at a Symposium on Whole Body Counting held in Vienna from 12 to 16 June 1961. The whole body counters can be divided into two broad groups: (a) counters for the radiation protection surveillance of the general public and radiation workers, capable of detecting extremely low levels of radioactivity in the human body, and (b) counters for medical research and diagnosis, designed to check the retention and excretion of radioactive substances administered to patients for metabolic and pathological studies. In both cases, the primary requirement is that the counter must be able to measure the total activity in the body. In recent years, there has been a remarkable development of the instruments and techniques for such measurements. One of the main purposes of the symposium in Vienna was to discuss how best to use these highly sophisticated instruments.

Vitrification of high-level radioactive and hazardous wastes

International Nuclear Information System (INIS)

Lutze, W.

1993-12-01

The main objective is to summarize work conducted on glasses as waste forms for high-level radioactive fission product solutions up to the late 1980's (section I and II). Section III addresses the question, whether waste forms designed for the immobilization of radioactive residues can be used for the same purpose for hazardous wastes. Of particular interest are those types of hazardous wastes, e.g., fly ashes from municipal combustion plants, easy to convert into glasses or ceramic materials. A large number of base glass compositions has been studied to vitrify waste from reprocessing but only borosilicate glasses with melting temperatures between 1100 C and 1200 C and very good hydrolytic stability is used today. (orig./HP) [de

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

Radioactive material in the West Lake Landfill: Summary report

International Nuclear Information System (INIS)

1988-06-01

The West Lake Landfill is located near the city of St. Louis in Bridgeton, St. Louis County, Missouri. The site has been used since 1962 for disposing of municipal refuse, industrial solid and liquid wastes, and construction demolition debris. This report summarizes the circumstances of the radioactive material in the West Lake Landfill. The radioactive material resulted from the processing of uranium ores and the subsequent by the AEC of processing residues. Primary emphasis is on the radiological environmental aspects as they relate to potential disposition of the material. It is concluded that remedial action is called for. 8 refs., 2 figs., 1 tab

Method of processing radioactive liquid wastes by solidification with cement

International Nuclear Information System (INIS)

Yasumura, Keijiro; Matsuura, Hiroyuki.

1975-01-01

Object: To subject radioactive liquid wastes to a cement solidification treatment after heating and drying it by a thin film scrape-off drier to render it into the form of power, and then molding it into pellets for the treatment. Structure: Radioactive liquid wastes discharged from a nuclear power plant or nuclear reactor are supplied through a storage tank into a thin film scrape-off drier. In the drier, the radioactive liquid wastes are heated to separate the liquid, and the residue is taken out as dry powder from the scrape-off apparatus. The powder obtained in this way is molded into pellets of a desired form. These pellets are then packed in a drum can or similar container, into which cement paste is then poured for solidification. (Moriyama, K.)

Criteria impacting shipments of Rocky Flats Plant radioactive mixed wastes

International Nuclear Information System (INIS)

Clawson, R.L.; Eide, J.H.

1992-05-01

Westinghouse Hanford Company, Transportation and Packaging Division, under contract for the Los Alamos Technology Office-Rocky Flats Plant, has developed this synopsis report to be used as a reference in the development of the Rocky Flats Plant Comprehensive Treatment and Management Plan and the Rocky Flats Plant Residue Elimination Plan. This report represents the criteria for packaging, shipping, and transporting Rocky Flats Plant radioactive mixed wastes. It is a compilation of state and federal regulations, US Department of Energy orders, and acceptance criteria specific to US Department of Energy radioactive mixed waste treatment, storage and disposal facilities

Method of reprocessing radioactive asphalt solidification products

International Nuclear Information System (INIS)

Nakaya, Iwao; Murakami, Tadashi; Miyake, Takafumi; Inagaki, Yuzo.

1986-01-01

Purpose: To obtain heat-stable solidification products and decrease the total volume thereof by modifying the solidified form by the reprocessing of existent radioactive asphalt solidification products. Method: Radioactive asphalt solidification products are heated into a fluidized state. Then, incombustible solvents such as perchloroethylene or trichloroethylene are added to a dissolving tank to gradually dissolve the radioactive asphalt solidification products. Thus, organic materials such as asphalts are transferred into the solvent layer, while inorganic materials containing radioactive materials remain as they are in the separation tank. Then, the inorganic materials containing the radioactive materials are taken out and then solidified, for example, by converting them into a rock or glass form. (Kawakami, Y.)

The Swedish programme for radioactive waste management

International Nuclear Information System (INIS)

Bjurstroem, S.; Forsstroem, H.

1986-10-01

The following systems and facilities are currently in operation and under implementation: a sea transportation system for all kinds of nuclear waste, a central facility for interim storage of spent fuel (CLAB) and a central underground repository for final disposal of low and medium level reactor waste (SFR). For the remaining steps - final disposal of highly active and longlived radioactive residues - a concept, based on encapsulation of the fuel elements in copper canisters and final storage of the canisters in a repository situated 500 m down in crystalline rock (KBS-3), has been developed and approved by the government in accordance with the Swedish nuclear legislation. Although a feasible method for final disposal of the highly active residues has been shown, the Swedish legislation requires that research be carried out to reach the best possible base for the final decision around the year 2000. In parallel with this a geological investigation programme is carried out to find a suitable site for a final repository. The final site selection is foreseen at the end of the 1990's. All costs for the management of radioactive waste from the nuclear power plants are carried by a fee determined annually. The fee is 0.019 SEK/kWh for 1986

Radioactivity, radiation protection and monitoring during dismantling of light-water reactors

International Nuclear Information System (INIS)

Hummel, L.; Zech, J.B.

2005-01-01

Based on the radioactivity inventory in the systems and components of light-water reactors observed during operation, the impact of actions during plant emptying after the conclusion of power operation and possible subsequent long-term safe enclosure concerning the composition of the nuclide inventory of the plant to be dismantled will be described. Derived from this will be the effects on radioactivity monitoring in the plant, physical radiation protection monitoring, and the measured characterization of the residual materials resulting from the dismantling. The impact of long-term interim storage will also be addressed in the discussion. The talk should provide an overview of the interrelationships between source terms, decay times and the radioactivity monitoring requirements of the various dismantling concepts for commercial light-water reactors. (orig.)

Dismantling, conditioning and repatriation of disused sealed radioactive sources

International Nuclear Information System (INIS)

Aguilar, S.L.; Miranda, C.A.; Saire, A.E.; Ontiveros, G.P.

2015-01-01

In Bolivia sealed radioactive sources for medical, industrial and research applications are used; radioactive sources containing a wide range of radionuclides and have different levels of activity and half-lives, they generated a problem when they stop being used. At the end of its useful life these sources are considered obsolete. However, residual levels of radioactivity, which have these sources can be high constituting a potential hazard to personnel and applies to those who benefit from its use and the general public. The aim of this work has been focused mainly on safety issues in the safe handling and management of disused sealed sources. Assignments listed below: 1. Dismantling; 2. Packaging; 3. Return of disused sealed radioactive sources. The actions taken were carried out by the technical teams of the Bolivian Institute of Nuclear Science and Technology (IBTEN) and Los Alamos National Laboratory (LANS) which supports the program 'Global Threat Reduction Initiative's' (GTRI) in the implementation of 'Off -site Source Recovery Program' (OSRP). [es

Shale as a radioactive waste repository: the importance of vermiculite

Energy Technology Data Exchange (ETDEWEB)

Komarneni, S; Roy, D M; Pennsylvania State Univ., University Park; USA). Materials Research Labs.)

1979-01-01

Cesium sorption and fixation properties of thirty shale minerals and shales were investigated in search of a criterion for the suitability of shales for a radioactive waste repository. Shales and illites containing vermiculite fixed the largest proportion of total Cs sorbed (up to 91%) against displacement with 0.1 N KCl. For example, a slate sample fixed 33% of the total Cs sorbed while its weathered counterpart in which chlorite had altered to vermiculite fixed 89% of the total Cs sorbed. Since Cs is one of the most soluble and hazardous radioactive ions, its containment is of great importance in safe radioactive waste disposal. Presence of vermiculite in a shale body may therefore, serve as one criterion in the selection of a suitable shale for radioactive waste disposal if and when shales in geologically stable areas are selected for repositories.

Modelling of radioactive fallout in the vicinity of Chernobyl nuclear power plant accident

International Nuclear Information System (INIS)

Israel, Y.A.; Petrov, V.N.; Severov, D.A.

1988-03-01

Deposition of radioactive products escaping into the atmosphere for a long time from the Chernobylsk-4 reactor resulting in residual radioactive contamination of the region at a distance of up to 100 km from the nuclear power plant is considered. The suggested model may be used for estimation of the possible scope of nuclear danger in the regions of nuclear power plants and creation of conditions ensuring safety of the population at possible accidents. The following topics are developed: height of elevation and conditions of radionuclide transfer in the atmosphere; dynamics of release and dispersive composition of radioactive products; calculations of radiation levels at a close trace [fr

Gross alpha radioactivity of drinking water in Venezuela

International Nuclear Information System (INIS)

Sajo-Bohus, L.; Gomez, J.; Greaves, E.D.; Herrera, O.; Salazar, V.; Smith, A.

1997-01-01

Bottled mineral water is consumed by a large population in Venezuela. The alpha emitters concentration was measured in samples of bottled water and water springs collected near the surface. Approximately 30% of the total mineral water suppliers was monitored. a database on natural and artificial radioactivity in drinking water was produced. Results indicate that 54% of the waters sampled contain a total alpha radioactivity of less than 0.185 Bql -1 and only 12% above 0.37 Bql -1 . Our results revealed a total annual dose of 2.3 mSv year -1 . (author)

Regulatory and management approaches to NORM residues in Malaysia

International Nuclear Information System (INIS)

Omar, M.; Teng, I.L.

2006-01-01

Naturally Occurring Radioactive Material (NORM) processing industries in Malaysia include oil and gas production and mineral processing plants. These industries are controlled by the Atomic Energy Licensing Board of Malaysia (AELB) through the enforcement of the Atomic Energy Licensing Act 1984 (Act 304). Related regulations have been developed in order to ensure the safety of workers and members of the public. However, more regulations are necessary for the safe handling of NORM. NORM processing generates various types of NORM residues that require proper management. As for low-level NORM residues, landfill disposal can be exempted from regulatory control if the Radiological Impact Assessment (RIA) shows that the additional dose to the members of the public is below the limit set by the authority. This paper outlines the regulatory and management approaches to NORM residues in Malaysia. (author)

Croatian radioactive waste management program: Current status

International Nuclear Information System (INIS)

Matanic, R.; Lebegner, J.

2001-01-01

Croatia has a responsibility to develop a radioactive waste management program partly due to co-ownership of Krsko nuclear power plant (Slovenia) and partly because of its own medical and industrial radioactive waste. The total amount of generated radioactive waste in Croatia is stored in temporary storages located at two national research institutes, while radioactive waste from Krsko remains in temporary storage on site. National power utility Hrvatska Elektroprivreda (HEP) and Hazardous Waste Management Agency (APO) coordinate the work regarding decommissioning, spent fuel management and low and intermediate level radioactive waste (LILRW) management in Croatia. Since the majority of work has been done in developing the LILRW management program, the paper focuses on this part of radioactive waste management. Issues of site selection, repository design, safety assessment and public acceptance are being discussed. A short description of the national radioactive waste management infrastructure has also been presented. (author)

International Conference on the Safety of Radioactive Waste Management. Book of Papers

International Nuclear Information System (INIS)

2016-01-01

The purpose of the conference was to highlight the importance of an integrated long term approach to the management of radioactive waste and spent fuel. The objectives of the conference were: • To foster information exchange between Member States, • To provide inputs that will promote further harmonization of safety in the fields of predisposal management and disposal of radioactive waste, • To highlight progress made in the safety of all types of radioactive waste. The conference served as a forum for discussing past experiences and future challenges. Furthermore, it seeked to identify Member States’ needs in order to assist them — through specific activities under future IAEA programmes in this area — to develop and implement safe solutions for the management of their entire radioactive waste inventory. The conference addressed all aspects of predisposal management and disposal of radioactive waste and spent fuel, including waste arising from accidental situations. The management of radioactive waste and residues from mining activities, as well as the control of discharges from nuclear facilities and activities, were, however, outside of its scope.

Tracking of Radioactive Sources in Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Mohd Fazlie Abdul Rashid; Noor Fadilla Ismail; Khairuddin Mohamad Kontol; Hairul Nizam Idris; Azimawati Ahmad; Suzilawati Muhd Sarowi; Raymond, Y.T.L.

2014-01-01

Radioactive materials are used in Malaysian Nuclear Agency for various purposes such as research and development, calibration, tracer and irradiation. Inventory of radioactive materials is crucial for ensuring the security and control of all radioactive materials owned and used so as not to be lost or fall into the hands of people who do not have permission to possess or use it. Experience in many countries around the world proves that the improper inventory of radioactive material would lead to loss of control of radioactive materials and will eventually cause an accident of radiation exposure. Radioactive material database has been developed for the need to ensure traceability of radioactive materials in Malaysian Nuclear Agency. Records of radioactive materials are regularly updated based on the classification of the type of radionuclide, the total distribution in each building and the initial activity of radioactive sources. (author)

Treatment of radioactive wastes by incineration; Tratamiento de desechos radiactivos por incineracion

Energy Technology Data Exchange (ETDEWEB)

Priego C, E., E-mail: emmanuel.priego@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2013-10-15

Great part of the radioactive wastes of low and intermediate level generated during the nuclear fuel cycle, in laboratories and other sites where the radionuclides are used for the research in the industry, in medicine and other activities, are combustible wastes. The incineration of these radioactive wastes provides a very high reduction factor and at the same time converts the wastes in radioactive ashes and no-flammable residuals, chemically inert and much more homogeneous that the initial wastes. With the increment of the costs in the repositories and those every time but strict regulations, the incineration of radioactive wastes has been able to occupy an important place in the strategy of the wastes management. However, in a particular way, the incineration is a complex process of high temperature that demands the execution of safety and operation requirements very specific. (author)

Method of removing radioactive waste from oil

International Nuclear Information System (INIS)

Belanger, R.L.

1986-01-01

This patent describes a method of removing particulates, radioactive contaminants, and moisture from oil, which consists of: straining out the particulates by passing the oil through a coarse filter screen to a receiving vessel; forming an upper stratum of oil and a lower stratum of sludge, consisting of mud, oil, particulates, and moisture, by heating the upper two-thirds of the receiving vessel; skimming off the stratum of oil from the receiving vessel; transferring the sludge from the receiving vessel to a container; transferring additional separated oil to the receiving vessel; conveying the oil skimmed from the receiving vessel to a mixing vessel; adding an effective amount of Calcium Hypochlorite crystals containing 65% free Chlorine to the mixing vessel to initiate salt formation with the radioactive contaminants; mixing the contents of the mixing vessel for at least ten minutes; transferring the mixture from the mixing vessel to a circulating heater; outputting the mixture from the circulating heater to a second mixing vessel; removing moisture from the oil; and filtering from the oil, the solid radioactive contaminant-salts and residual particulate matter

Control levels for residual contamination in materials considered for recycle and reuse

International Nuclear Information System (INIS)

Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.

1993-09-01

Pacific Northwest Laboratory (PNL) is collecting data and conducting technical analyses to support joint efforts by the U.S. Department of Energy (DOE), Office of Environmental Guidance, Air, Water and Radiation Division (DOE/EH-232); by the U.S. Environmental Protection Agency (EPA); and by the U.S. Nuclear Regulatory Commission (NRC) to develop radiological control criteria for the recycle and reuse of scrap materials and equipment that contain residual radioactive contamination. The initial radiological control levels are the concentrations in or on materials considered for recycle or reuse that meet the individual (human) or industrial (electronics/film) dose criteria. The analysis identifies relevant radionuclides, potential mechanisms of exposure, and methods to determine possible non-health-related impacts from residual radioactive contamination in materials considered for recycle or reuse. The generic methodology and scenarios described here provide a basic framework for numerically deriving radiological control criteria for recycle or reuse. These will be adequately conservative for most situations

Residues of 14C-cyolane in cottonseed products

International Nuclear Information System (INIS)

Zayed, S.M.A.D.; Osman, A.Z.; Fakhr, I.M.I.; Bahig, M.E.

1981-01-01

The systemic insecticide cyolane [2-(0,0-diethylphosphoryl)-imino-1,3-dithiolane] was prepared from 14 C-ethanol, phosphorus oxychloride and 2-amino-1,3-dithiolane. Cotton plants were treated with two applications of the insecticide under conditions of local agricultural practice. 14 C-residues in the crude oil and cake of the harvested cotton seeds amounted to 1.63 and 0.014 mg/kg respectively. About 50% of the 14 C-activity present in the crude oil was found to be eliminated by simulated commercial processes used for refining of the oil. Alkali treatment and bleaching removed 16% and 25% of the radioactive residues respectively. Winterization of the bleached oil at 5-7 0 C for 3 days effected a further elimination of 13%. 14 C-residues in the cotton seed products and in the samples of the refined oil were characterized and the main constituents identified using chromatographic techniques. (author)

Setting of cesium residual ratio of molten solidified waste produced in Japan Atomic Power Company Tokai and Tokai No.2 Power Stations

International Nuclear Information System (INIS)

2013-02-01

JNES investigated the appropriateness of a view of the Japan Nuclear Fuel Co. on cesium residual content and the radioactivity measurement precision regarding the molten solidified (with lowered inorganic salt used) radioactive wastes which were produced from Japan Atomic Power Company Tokai and Tokai No. 2 Power Stations. Based on the written performance report from the request and past disposal confirmation experience, a view of the JNFC is confirmed as appropriate that setting of 15% cesium residual ratio for molten solidified with volume ratio larger than 4% and less than 10% cases. (S. Ohno)

Radiological considerations on multi-MW targets Part I Induced radioactivity

CERN Document Server

Agosteo, S; Silari, M

2005-01-01

CERN is designing a Superconducting Proton Linac (SPL) to provide a 2.2GeV, 4MW proton beam to feed facilities like, for example, a future Neutrino Factory or a Neutrino SuperBeam. The material activation in such facilities is an important aspect that has to be taken into account at an early design stage. In particular, the choice of the target has consequences on the induced radioactivity and dose rates in the target itself and in its surroundings. In the present work, the radiological aspects of a stationary target made up of small tantalum pellets are compared to those of a free-surface jet of mercury. An estimation of the hadronic inelastic interactions and the production of residual nuclei in the target, the magnetic horn, the decay tunnel, the surrounding rock and a downstream dump were performed for both targets by the Monte Carlo hadronic cascade code FLUKA. The aim was to assess the dose equivalent rate to be expected during maintenance work and to evaluate the amount of residual radioactivity, which...

Distribution of residual long-lived radioactivity in the inner concrete walls of a compact medical cyclotron vault room.

Science.gov (United States)

Fujibuchi, Toshioh; Nohtomi, Akihiro; Baba, Shingo; Sasaki, Masayuki; Komiya, Isao; Umedzu, Yoshiyuki; Honda, Hiroshi

2015-01-01

Compact medical cyclotrons have been set up to generate the nuclides necessary for positron emission tomography. In accelerator facilities, neutrons activate the concrete used to construct the vault room; this activation increases with the use of an accelerator. The activation causes a substantial radioactive waste management problem when facilities are decommissioned. In the present study, several concrete cores from the walls, ceiling and floor of a compact medical cyclotron vault room were samples 2 years after the termination of operations, and the radioactivity concentrations of radionuclides were estimated. Cylindrical concrete cores 5 cm in diameter and 10 cm in length were bored from the concrete wall, ceiling and floor. Core boring was performed at 18 points. The gamma-ray spectrum of each sample was measured using a high-purity germanium detector. The degree of activation of the concrete in the cyclotron vault room was analyzed, and the range and tendency toward activation in the vault room were examined. (60)Co and (152)Eu were identified by gamma-ray spectrometry of the concrete samples. (152)Eu and (60)Co are produced principally from the stable isotopes of europium and cobalt by neutron capture reactions. The radioactivity concentration did not vary much between the surface of the concrete and at a depth of 10 cm. Although the radioactivity concentration near the target was higher than the clearance level for radioactive waste indicated in IAEA RS-G-1.7, the mean radioactivity concentration in the walls and floor was lower than the clearance level. The radioactivity concentration of the inner concrete wall of the medical cyclotron vault room was not uniform. The areas exceeding the clearance level were in the vicinity of the target, but most of the building did not exceed the clearance levels.

Forest decline, natural and technically generated radioactivity

International Nuclear Information System (INIS)

Teufel, D.

1983-06-01

The question investigated is whether the radioactive rare gases emanating from nuclear plants are causative or participate in the triggering of forest disease. For one thing, a chemical reaction could be responsible for such an effect exerted by these artificial radioactive effluents. However, a calculation shows the concentration of radionuclides, respectively, in this case, their decomposition products, to be by many orders of magnitude smaller than other constituents in air; so a chemical reaction of this kind may be excluded. For the other part, rare gases might contribute to forest damage by their radioactive decomposition and late physical, chemical, and biological effects. In this connection, a detailed analysis is made of the comparability of natural radioactivity with radioactivity generated by nuclear plants. A possible contribution towards the total stress situation of forests (chemical air pollution, natural radioactivity, artificially produced radioactive rare gases, weather conditions and conditions arising from forest management and the like) would amount to a proportion smaller than 1/1000 considering natural radioactivity as a possible stress factor only. (orig.) [de

Carbaryl residues in maize products

International Nuclear Information System (INIS)

Zayed, S.M.A.D.; Mansour, S.A.; Mostafa, I.Y.; Hassan, A.

1976-01-01

The 14 C-labelled insecticide carbaryl was synthesized from [1- 14 C]-1-naphthol at a specific activity of 3.18mCig -1 . Maize plants were treated with the labelled insecticide under simulated conditions of agricultural practice. Mature plants were harvested and studied for distribution of total residues in untreated grains as popularly roasted and consumed, and in the corn oil and corn germ products. Total residues found under these conditions in the respective products were 0.2, 0.1, 0.45 and 0.16ppm. (author)

Analysis of the total system life cycle cost for the Civilian Radioactive Waste Management Program: executive summary

International Nuclear Information System (INIS)

1985-04-01

The total-system life-cycle cost (TSLCC) analysis for the Department of Energy's Civilian Radioactive Waste Management Progrram is an ongoing activity that helps determine whether the revenue-producing mechanism established by the Nuclear Waste Policy Act of 1982 is sufficient to cover the cost of the program. This report is an input into the third evaluation of the adequacy of the fee. The total-system cost for the reference waste-management program in this analysis is estimated to be 24 to 30 billion (1984) dollars. For the sensitivity cases studied in this report, the costs could be as high as 35 billion dollars and as low as 21 billion dollars. Because factors like repository location, the quantity of waste generated, transportation-cask technology, and repository startup dates exert substantial impacts on total-system costs, there are several tradeoffs between these factors, and these tradeoffs can greatly influence the total cost of the program. The total-system cost for the reference program described in this report is higher by 3 to 5 billion dollars, or 15 to 20%, than the cost for the reference program of the TSLCC analysis of April 1984. More than two-thirds of this increase is in the cost of repository construction and operation. These repository costs have increased because of changing design concepts, different assumptions about the effort required to perform the necessary activities, and a change in the source data on which the earlier analysis was based. Development and evaluation costs have similarly increased because of a net addition to the work content. Transportation costs have increased because of different assumptions about repository locations and several characteristics of the transportation system. It is expected that the estimates of total-system costs will continue to change in response to both an evolving program strategy and better definition of the work required to achieve the program objectives

Environmental impact assessment for a radioactive waste facility: A case study

International Nuclear Information System (INIS)

Devgun, J.S.

1990-01-01

A 77-ha site, known as the Niagara Falls Storage Site and located in northwestern New York State, holds about 190, 000 m 3 of soils, wastes, and residues contaminated with radium and uranium. The facility is owned by the US Department of Energy. The storage of residues resulting from the processing of uranium ores started in 1944, and by 1950 residues from a number of plants were received at the site. The residues, with a volume of about 18,000 m 3 , account for the bulk of the radioactivity, which is primarily due to Ra-226; because of the extraction of uranium from the ore, the amount of uranium remaining in the residues is quite small. An analysis of the environmental impact assessment and environmental compliance actions taken to date at this site and their effectiveness are discussed. This case study provides an illustrative example of the complexity of technical and nontechnical issues for a large radiative waste facility. 11 refs., 7 figs., 2 tabs

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

Radioactive Cs in the estuary sediments near Fukushima Daiichi Nuclear Power Plant

International Nuclear Information System (INIS)

Yamasaki, Shinya; Imoto, Junpei; Furuki, Genki; Ochiai, Asumi; Ohnuki, Toshihiko; Sueki, Keisuke; Nanba, Kenji; Ewing, Rodney C.; Utsunomiya, Satoshi

2016-01-01

The migration and dispersion of radioactive Cs (mainly "1"3"4Cs and "1"3"7Cs) are of critical concern in the area surrounding the Fukushima Daiichi Nuclear Power Plant (FDNPP). Considerable uncertainty remains in understanding the properties and dynamics of radioactive Cs transport by surface water, particularly during rainfall-induced flood events to the ocean. Physical and chemical properties of unique estuary sediments, collected from the Kuma River, 4.0 km south of the FDNPP, were quantified in this study. These were deposited after storm events and now occur as dried platy sediments on beach sand. The platy sediments exhibit median particle sizes ranging from 28 to 32 μm. There is increasing radioactivity towards the bottom of the layers deposited; approximately 28 and 38 Bq g"−"1 in the upper and lower layers, respectively. The difference in the radioactivity is attributed to a larger number of particles associated with radioactive Cs in the lower part of the section, suggesting that radioactive Cs in the suspended soils transported by surface water has decreased over time. Sequential chemical extractions showed that ~ 90% of "1"3"7Cs was strongly bound to the residual fraction in the estuary samples, whereas 60 ~ 80% of "1"3"7Cs was bound to clays in the six paddy soils. This high concentration in the residual fraction facilitates ease of transport of clay and silt size particles through the river system. Estuary sediments consist of particles < 100 μm. Radioactive Cs desorption experiments using the estuary samples in artificial seawater revealed that 3.4 ± 0.6% of "1"3"7Cs was desorbed within 8 h. More than 96% of "1"3"7Cs remained strongly bound to clays. Hence, particle size is a key factor that determines the travel time and distance during the dispersion of "1"3"7Cs in the ocean. - Highlights: • Cs-137 of estuary sediment impacted by the FDNPP was measured. • Physical and chemical properties were measured also. • Increasing radioactivity was

Radioactive Cs in the estuary sediments near Fukushima Daiichi Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Yamasaki, Shinya, E-mail: s-yamasaki@ied.tsukuba.ac.jp [Faculty of Pure and Applied Sciences and Center for Research in Isotopes and Environmental Dynamics, University of Tsukuba, 1-1-1 Tennodai, Tsukuba, Ibaraki 305-8577 (Japan); Imoto, Junpei; Furuki, Genki; Ochiai, Asumi [Department of Chemistry, Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581 (Japan); Ohnuki, Toshihiko [Advanced Science Research Center, Japan Atomic Energy Agency, Shirakata Shirane 2-4, Tokai, Ibaraki 319-1195 (Japan); Sueki, Keisuke [Faculty of Pure and Applied Sciences and Center for Research in Isotopes and Environmental Dynamics, University of Tsukuba, 1-1-1 Tennodai, Tsukuba, Ibaraki 305-8577 (Japan); Nanba, Kenji [Department of Environmental Management, Faculty of Symbiotic System Science, Fukushima University, Kanayagawa 1, Fukushima, 960-1296 (Japan); Ewing, Rodney C. [Department of Geological Sciences and Center for International Security and Cooperation, Stanford University, Stanford, CA 94305-2115 (United States); Utsunomiya, Satoshi [Department of Chemistry, Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581 (Japan)

2016-05-01

The migration and dispersion of radioactive Cs (mainly {sup 134}Cs and {sup 137}Cs) are of critical concern in the area surrounding the Fukushima Daiichi Nuclear Power Plant (FDNPP). Considerable uncertainty remains in understanding the properties and dynamics of radioactive Cs transport by surface water, particularly during rainfall-induced flood events to the ocean. Physical and chemical properties of unique estuary sediments, collected from the Kuma River, 4.0 km south of the FDNPP, were quantified in this study. These were deposited after storm events and now occur as dried platy sediments on beach sand. The platy sediments exhibit median particle sizes ranging from 28 to 32 μm. There is increasing radioactivity towards the bottom of the layers deposited; approximately 28 and 38 Bq g{sup −1} in the upper and lower layers, respectively. The difference in the radioactivity is attributed to a larger number of particles associated with radioactive Cs in the lower part of the section, suggesting that radioactive Cs in the suspended soils transported by surface water has decreased over time. Sequential chemical extractions showed that ~ 90% of {sup 137}Cs was strongly bound to the residual fraction in the estuary samples, whereas 60 ~ 80% of {sup 137}Cs was bound to clays in the six paddy soils. This high concentration in the residual fraction facilitates ease of transport of clay and silt size particles through the river system. Estuary sediments consist of particles < 100 μm. Radioactive Cs desorption experiments using the estuary samples in artificial seawater revealed that 3.4 ± 0.6% of {sup 137}Cs was desorbed within 8 h. More than 96% of {sup 137}Cs remained strongly bound to clays. Hence, particle size is a key factor that determines the travel time and distance during the dispersion of {sup 137}Cs in the ocean. - Highlights: • Cs-137 of estuary sediment impacted by the FDNPP was measured. • Physical and chemical properties were measured also. �

Inulin-125I-tyramine, an improved residualizing label for studies on sites of catabolism of circulating proteins

International Nuclear Information System (INIS)

Maxwell, J.L.; Baynes, J.W.; Thorpe, S.R.

1988-01-01

Residualizing labels for protein, such as dilactitol-125I-tyramine (125I-DLT) and cellobiitol-125I-tyramine, have been used to identify the tissue and cellular sites of catabolism of long-lived plasma proteins, such as albumin, immunoglobulins, and lipoproteins. The radioactive degradation products formed from labeled proteins are relatively large, hydrophilic, resistant to lysosomal hydrolases, and accumulate in lysosomes in the cells involved in degradation of the carrier protein. However, the gradual loss of the catabolites from cells (t1/2 approximately 2 days) has limited the usefulness of residualizing labels in studies on longer lived proteins. We describe here a higher molecular weight (Mr approximately 5000), more efficient residualizing glycoconjugate label, inulin-125I-tyramine (125I-InTn). Attachment of 125I-InTn had no effect on the plasma half-life or tissue sites of catabolism of asialofetuin, fetuin, or rat serum albumin in the rat. The half-life for hepatic retention of degradation products from 125I-InTn-labeled asialofetuin was 5 days, compared to 2.3 days for 125I-DLT-labeled asialofetuin. The whole body half-lives for radioactivity from 125I-InTn-, 125I-DLT-, and 125I-labeled rat serum albumin were 7.5, 4.3, and 2.2 days, respectively. The tissue distribution of degradation products from 125I-InTn-labeled proteins agreed with results of previous studies using 125I-DLT, except that a greater fraction of total degradation products was recovered in tissues. Kinetic analyses indicated that the average half-life for retention of 125I-InTn degradation products in tissues is approximately 5 days and suggested that in vivo there are both slow and rapid routes for release of degradation products from cells

Effect of cooking on14 C-tetrachlorvinphos residues in faba beans

International Nuclear Information System (INIS)

Farghaly, M.; Zayed, S.M.A.D.

1986-01-01

The effect of cooking on 14 C-tetrachlorvinphos in stored vicia faba beans was studied. The results indicated that over 50% of the dose originally present inside the grains (37 ppm), could be recovered in the aqueous extract of the cooked grains. Considerable portion of radioactivity (About 22%) was associated with the grains in a non-extractable from. Residues in cooked beans included, in addition to a small amount of the parent insecticide, desmethyl tetrachlorvinphos, mono methyl phosphate and dimethyl phosphate. The results obtained indicate that tetrachlorvinphos residues are not appreciably affected by cooking. 1 tab

Long-term evaluation for engineered capping (cover) of radioactive repository or landfill

International Nuclear Information System (INIS)

Mohd Jamil Hashim; Mohd Abdul Wahab Yusof

2010-01-01

This paper discussed the long-term evaluation of engineered capping for radioactive repository. It was done to gather knowledge and understand the suitability of granitic residual soil. Its resistance to hydrologic cycle and durability through a period of 100 to 300 years was checked. A hydrological program was used with forecast weather and manual checking all layers for hydraulic gradient to verify the results. Overall result shown that the grantic residual soil is able to last a few centuries before surcome to infiltration. (author)

Study of immobilization of radioactive wastes in asphaltic matrices and elastomeric residues by using microwave technique

International Nuclear Information System (INIS)

Caratin, Reinaldo Leonel

2007-01-01

In the present work, the technique of microwave heating was used to study the immobilization of low and intermediate activity level radioactive waste, such as spent ion exchange resin used to remove undesirable ions of primary circuits of refrigeration in water refrigerated nuclear reactors, and those used in chemical and radionuclide separation columns in the quality control of radioisotopes. Bitumen matrices reinforced with some kinds of rubber (Neoprene R , silicon and ethylene-vinyl-acetate), from production leftovers or scraps, were used for incorporation of radioactive waste. The samples irradiation was made in a home microwave oven that operates at a frequency of 2.450 MHZ with 1.000 W power. The samples were characterized by developing assays on penetration, leaching resistance, softening, flash and combustion points, thermogravimetry and optical microscopy. The obtained results were compatible with the pattern of matrices components, which shows that technique is a very useful alternative to conventional immobilization methods and to those kinds of radioactive waste. (author)

Always more radioactive matters to manage

International Nuclear Information System (INIS)

Chevallier, J.

2009-01-01

The national agency for radioactive waste management published at the end of June (2009)its new three-yearly inventory of radioactive matters and wastes. for this edition, the numbers are stopped at the 31. december 2007. The volume of conditioned wastes represents 1.15 millions of cubic meters. 62% of these wastes come from nuclear industry. The sectors of research and defence each produce 17% of the whole. The remaining 4% come from others industries and medical sector. currently, 824 609 cubic meters are stored. The most being low and intermediate activity at short life (68%) and very low activity (20%). with 2293 cubic meters the high level activity wastes represent 0.2% of the total volume but constitute 94.98% of the total radioactivity. They come from the reprocessing of spent fuels of electronuclear industry and content fission products and minor actinides. They are not still stored but mixed to a glass matrix melt in stainless steel container. (N.C.)

Radioactive inputs to the North Sea and the Channel

International Nuclear Information System (INIS)

1984-01-01

The subject is covered in sections: introduction (radioactivity; radioisotopes; discharges from nuclear establishments); data sources (statutory requirements); sources of liquid radioactive waste (figure showing location of principal sources of radioactive discharges; tables listing principal discharges by activity and by nature of radioisotope); Central Electricity Generating Board nuclear power stations; research and industrial establishments; Ministy of Defence establishments; other UK inputs of radioactive waste; total inputs to the North Sea and the Channel (direct inputs; river inputs; adjacent sea areas); conclusions. (U.K.)

Review of the incineration of 500 tonnes of radio-active residues; Bilan de l'incineration de 500 tonnes de residus radioactifs

Energy Technology Data Exchange (ETDEWEB)

Rodier, J; Seyfried, P; Charbonneaux, M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

1969-07-01

During its first five years operation, the incinerator at the Marcoule Centre has burnt almost 500 tonnes of radio-active residues. Improvements in some of the details of the process have been made during this period; they concern the nature of the materials involved. The technical and radiological results for the installation are very favorable, and have made it possible to maintain a high charge factor.Although the overall economic results are not advantageous in the case of ungraded solid residues this method represents nevertheless the best available for eliminating oils, solvents, wood and dead animals. It can also be of use furthermore each time that a dilution in the atmosphere can advantageously be used as a method of disposing of certain radio elements such as tritium or carbon 14 in the form of gases or vapours. (author) [French] L'incinerateur du Centre de Marcoule a brule, durant les 5 premieres annees de fonctionnement, pres de 500 tonnes de residus radioactifs. Les ameliorations de detail realisees au cours de cette periode ont porte sur la nature des materiaux employes. Les bilans techniques et radiologiques de l'installation sont tres favorables et ont permis de maintenir un facteur de charge eleve. Si le bilan economique n'est pas favorable a l'incineration des residus solides 'tout venant' cette methode constitue cependant la solution ideale pour l'elimination des huiles, des solvants, du bois et des cadavres d'animaux. En outre, elle peut etre interessante chaque fois que la dilution dans l'atmosphere peut etre avantageusement mise a profit pour rejeter certains radioelements tels que le tritium ou le carbone 14 sous forme de gaz ou de vapeurs. (auteur)

Effects of cooking process on the changes of concentration and total amount of radioactive caesium in beef, wild plants and fruits

International Nuclear Information System (INIS)

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

2016-01-01

In order to obtain information about effects of the cooking process on the changes of concentration and amount of radioactive materials in foods, we determined the concentration of radioactive caesium in several foods such as beef, edible wild plants, blueberries and mushrooms, before and after cooking. Our results showed that drying after soaking in liquid seasoning and the removal of astringent taste were effective in removing radioactive caesium from foods. More than 80% of radioactive caesium could be removed by these cooking methods. These results suggest that cooking processes such as boiling and soaking in liquid seasoning or water are effective to remove radioactive caesium from foods. Moreover, appropriate food additives such as baking soda were useful to promote the removal of radioactive caesium from foods. On the other hand, simple drying, jam making, grilling and tempura cooking could not remove radioactive caesium from foods. In addition, we showed that the concentration of radioactive caesium in foods was raised after simple drying, although the amount of radioactive caesium was unchanged. It would be necessary to monitor radioactive caesium concentration in processed foods because they might have undergone dehydration by cooking, which could result in concentrations exceeding regulatory levels. (author)

Development for low-activation concrete design reducing radioactive waste

International Nuclear Information System (INIS)

Kimura, Ken-ichi; Kinno, Masaharu; Hasegawa, Akira

2008-01-01

Full text: Concrete is very valuable and inexpensive material, however it can be changed to be expensive and hard to deal with in use of a nuclear plant after long operation. One of the counter plans for the above is to use low-activation concrete instead of the ordinary concrete, that will reduce radioactive waste and could be even below clearance level in decommissioning and that is very useful in term of life cycle cost. Radioactive analysis showed that Co and Eu were the major target elements which decide the radioactivity level of reinforced concrete in decommissioning stage, and a several material were selected as a low-activation raw material from wide survey of raw materials for concrete (typically aggregates and cements). With the canditate of raw materials, several low-activation concrete were proposed for various portion of light water reactor plant, which reduction ratio were 1/10 to 1/30 which were mainly consist of limestone and low heat cement or white cement, and 1/100 to 1/300 which were mainly consist of alumina aggregate or quartz and high almina cement, comparing to the ordinary concrete in ΣDi/Ci unit, where 'Di' indicates concentration of each residual radioisotope, Ci defined by IAEA as a clearance level, and suffition of 'i' indicates each radioisotope. National funded project for development of low-activation design method for reduction of radioactive waste below clearance level were started from 2005 with aiming (1) development of a database on the content of target elements, which transform radioactive nuclides, in raw materials of reinforced concrete, (2) development of calculation tools for estimation of residual radioactivity of plant components, and (3) development of low-activation materials for concrete such as cements and reinforcing steel bars for structural components. For the optimized design for applying low-activation concrete to the reactor portion, effective evaluation of neutron spectrum in the certain portion including

Results of radioactivity surveys in Miyagi Prefecture

International Nuclear Information System (INIS)

1983-01-01

The results of radioactivity surveys carried out in Miyagi Prefecture in fiscal 1981 (from April, 1981, to March, 1982), entrusted by the Science and Technology Agency, are presented in tables: total β radioactivity in rainwater, in rainwater and dust collected by large basins, in daily foods, in land water, in dairy products and vegetables, in marine products and in soil, 131 I nuclide in cow's milk, air γ-ray dose rate by survey meters, and air γ-ray counting, rate by a monitoring post were examined. The total β radioactivity was measured by a GM counting apparatus with an automatic sample changer, the nuclide analysis by a NaI(Tl) scintillation spectrometer, the air γ-ray dose rate by a NaI(Tl) scintillation survey meter, and the γ-ray counting rate by a NaI(Tl) scintillation type monitoring post. (Mori, K.)

Preliminary estimates of the total-system cost for the restructured program: An addendum to the May 1989 analysis of the total-system life cycle cost for the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

1990-12-01

The total-system life-cycle cost (TSLCC) analysis for the Department of Energy's (DOE) Civilian Radioactive Waste Management Program is an ongoing activity that helps determine whether the revenue-producing mechanism established by the Nuclear Waste Policy Act of 1982 - a fee levied on electricity generated and sold by commercial nuclear power plants - is sufficient to cover the cost of the program. This report provides cost estimates for the sixth annual evaluation of the adequacy of the fee. The costs contained in this report represent a preliminary analysis of the cost impacts associated with the Secretary of Energy's Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program issued in November 1989. The major elements of the restructured program announced in this report which pertain to the program's life-cycle costs are: a prioritization of the scientific investigations program at the Yucca Mountain candidate site to focus on identification of potentially adverse conditions, a delay in the start of repository operations until 2010, the start of limited waste acceptance at the monitored retrievable storage (MRS) facility in 1998, and the start of waste acceptance at the full-capability MRS facility in 2,000. Based on the restructured program, the total-system cost for the system with a repository at the candidate site at Yucca Mountain in Nevada, a facility for monitored retrievable storage (MRS), and a transportation system is estimated at $26 billion (expressed in constant 1988 dollars). In the event that a second repository is required and is authorized by the Congress, the total-system cost is estimated at $34 to $35 billion, depending on the quantity of spent fuel and high-level waste (HLW) requiring disposal. 17 figs., 17 tabs

Environmental toxicity and radioactivity assessment of a titanium-processing residue with potential for environmental use.

Science.gov (United States)

Wendling, Laura A; Binet, Monique T; Yuan, Zheng; Gissi, Francesca; Koppel, Darren J; Adams, Merrin S

2013-07-01

Thorough examination of the physicochemical characteristics of a Ti-processing residue was undertaken, including mineralogical, geochemical, and radiochemical characterization, and an investigation of the environmental toxicity of soft-water leachate generated from the residue. Concentrations of most metals measured in the leachate were low; thus, the residue is unlikely to leach high levels of potentially toxic elements on exposure to low-ionic strength natural waters. Relative to stringent ecosystem health-based guidelines, only chromium concentrations in the leachate exceeded guideline concentrations for 95% species protection; however, sulfate was present at concentrations known to cause toxicity. It is likely that the high concentration of calcium and extreme water hardness of the leachate reduced the bioavailability of some elements. Geochemical modeling of the leachate indicated that calcium and sulfate concentrations were largely controlled by gypsum mineral dissolution. The leachate was not toxic to the microalga Chlorella sp., the cladoceran Ceriodaphnia dubia, or the estuarine bacterium Vibrio fischeri. The Ti-processing residue exhibited an absorbed dose rate of 186 nGy/h, equivalent to an annual dose of 1.63 mGy and an annual effective dose of 0.326 mGy. In summary, the results indicate that the Ti-processing residue examined is suitable for productive use as an environmental amendment following 10 to 100 times dilution to ameliorate potential toxic effects due to chromium or sulfate. Copyright © 2013 SETAC.

Optimization of Concrete Composition in Radioactive Waste Management

International Nuclear Information System (INIS)

IIija, P.

1999-01-01

Low and Intermediate level radioactive waste re presents 95% of the total wastes that is conditioned into special concrete containers. Since these containers are to protect radioactive waste safely for about 300 years, the selection and precise control of physical and mechanical characteristics of materials is very important. After volume reduction and valuable components recovery, waste materials have to be conditioned for transport, storage and disposal. Conditioning is the waste management step in which radioactive wastes are immobilized and packed . In this paper methods and optimization of concrete container composition, used for storing radioactive waste, is presented

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

Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

International Nuclear Information System (INIS)

Bell, J.T.; Haas, P.A.; Rudolph, J.C.

1993-01-01

The Oak Ridge National Laboratory (ORNL) is involved in a program to apply a molten salt oxidation (MSO) process to the treatment of mixed wastes at Oak Ridge and other Department of Energy (DOE) sites. Mixed wastes are defined as those wastes that contain both radioactive components, which are regulated by the atomic energy legislation, and hazardous waste components, which are regulated under the Resource Conservation and Recovery Act (RCRA). A major part of our ORNL program involves the development of separation technologies that are necessary for the complete treatment of mixed wastes. The residues from the MSO treatment of the mixed wastes must be processed further to separate the radioactive components, to concentrate and recycle residues, or to convert the residues into forms acceptable for final disposal. This paper is a review of the MSO requirements for separation technologies, the information now available, and the concepts for our development studies

Method for the reprocessing of liquid wastes containing boric acid, radioactive antimony and other radioactive nuclides and similar, especially of the evaporator concentrates of nuclear power plants

International Nuclear Information System (INIS)

Doerr, A.

1978-01-01

The liquid wastes are evaporated, H 2 SO 4 and methanol are added, and the formed boric acid methylester is distilled off. The residue with Sb-124, Cs, Co and Mn is then stored two years until the activity of Sb-124 has decayed. Afterwards the radioactive nuclides are precipitated. (DG) [de

Determination of hepatic blood flow through radioactive colloidal gold in congestive heart foilure

International Nuclear Information System (INIS)

Papaleo Netto, M.; Carvalho, N.; Carvalho Filho, E.T.; Forti, N.A.; Giannini, S.D.; Diament, J.; Decourt, L.V.; Chiaverini, R.

1974-01-01

Hepatic blood flow as derermined by radioactive colloidal gold and its correlation with total blood valume are studied in 13 patients with predominantly right-side congestive heart failure. During the phase of cardiac compensation, the following events occur: 1) significant decrease of the half-life of the clearance of radioactive colloidal gold and of the total blood volume; 2) increase of the clearance constant of the radioactive substance and of hepatic blood flow; 3) significantion correlation between the clearance constant and the total blood volume [pt

Status of 2009 radioactivity monitoring in French Polynesia. Results of IRSN's monitoring network

International Nuclear Information System (INIS)

2010-01-01

Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes, consists in regularly collecting samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagoes of that territory. They come from the marine environment of the open sea, from the marine lagoon environment and from the terrestrial environment. Almost all samples are measured at the IRSN Laboratory for the Environment Study and Monitoring, based in Vairao, Tahiti Island. The 239 samples collected in 2009 were measured by Hp-Ge low background gamma spectrometry in order to be able to characterize lowest possible radioactivity levels. The levels of activity of Pu isotopes have also been determined for 17 selected samples and tritium activities for 15 water samples. The results for the year 2009 are in the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro Sieverts per year). This value corresponds to less than 0, 5 % of exposure due to natural radioactivity in Polynesia (approximately 1000 μSv.y -1 ). (authors)

A laboratory activity for teaching natural radioactivity

Science.gov (United States)

Pilakouta, M.; Savidou, A.; Vasileiadou, S.

2017-01-01

This paper presents an educational approach for teaching natural radioactivity using commercial granite samples. A laboratory activity focusing on the topic of natural radioactivity is designed to develop the knowledge and understanding of undergraduate university students on the topic of radioactivity, to appreciate the importance of environmental radioactivity and familiarize them with the basic technology used in radioactivity measurements. The laboratory activity is divided into three parts: (i) measurements of the count rate with a Geiger-Muller counter of some granite samples and the ambient background radiation rate, (ii) measurement of one of the samples using gamma ray spectrometry with a NaI detector and identification of the radioactive elements of the sample, (iii) using already recorded 24 h gamma ray spectra of the samples from the first part (from the Granite Gamma-Ray Spectrum Library (GGRSL) of our laboratory) and analyzing selected peaks in the spectrum, students estimate the contribution of each radioactive element to the total specific activity of each sample. A brief description of the activity as well as some results and their interpretation are presented.

Decommissioning Strategies Selection for Facilities Using Radioactive Material

International Nuclear Information System (INIS)

Husen Zamroni; Jaka Rachmadetin

2008-01-01

The facilities using radioactive material that have been stopped operation will require some form of the decommissioning for public and environment safety. The approaches are identified by three decommissioning strategies: immediate dismantling, deferred dismantling and entombment. If a facility undergoes immediate dismantling, most radio nuclides will have no such sufficient time to decay and therefore this strategy may not provide reduction in the worker exposure. A facility that undergoes deferred dismantling may advantage from the radioactive decay of residual radio nuclides during the long term storage period and entombment could be a viable option for other nuclear facilities containing only short lived or limited concentrations of long lived radionuclides. Mostly, only two types of the decommissioning used to be done in the world, immediate and deferred dismantling. (author)

Transformation of bisdithiocarbamate fungicides and the chemical nature of their residues in plants

International Nuclear Information System (INIS)

Vonk, J.W.

1975-01-01

Studies on the fate of 1,2- 14 C-disodium ethylenebisdithiocarbamate (nabam) applied to roots and leaves of cucumber plants under laboratory conditions have revealed that ethylenethiourea (ETU) and dihydro-3 H-imidazodithiazole (DIDT) were major initial breakdown products. On applying nabam to roots, residues in the plants consisted mainly of ETU, which was rapidly metabolized to 2-imidazoline and ethyleneurea. Moreover, a considerable amount of unidentified, mostly polar material was found. After 19 days, 87% of the total radioactivity taken up could be recovered. Of this only 22% could be identified. Two weeks after applying nabam to leaves, about 89% of the applied activity could be recovered. ETU, DIDT, a small amount of 2-imidazoline, and unknown polar material were present in or on the treated leaf. Only 0.3% had moved into the untreated parts. (author)

Method of processing radioactive metal wastes

International Nuclear Information System (INIS)

Inoue, Yoichi; Kitagawa, Kazuo; Tsuzura, Katsuhiko.

1980-01-01

Purpose: To enable long and safety storage for radioactive metal wastes such as used fuel cans after the procession or used pipe, instruments and the likes polluted with various radioactive substances, by compacting them to solidify. Method: Metal wastes such as used fuel cans, which have been cut shorter and reprocessed, are pressed into generally hexagonal blocks. The block is charged in a capsule of a hexagonal cross section made of non-gas permeable materials such as soft steels, stainless steels and the likes. Then, the capsule is subjected to static hydraulic hot pressing as it is or after deaeration and sealing. While various combinations are possible for temperature, pressure and time as the conditions for the static hydraulic hot pressing, dense block with no residual gas pores can be obtained, for example, under the conditions of 900 0 C, 1000 Kg/cm 2 and one hour where the wastes are composed of zircaloy. (Kawakami, Y.)

Transmutation of radioactive wastes: how and why?

International Nuclear Information System (INIS)

Patarin, L.

2004-01-01

After having evoked the natural or spontaneous transmutation of natural or artificial radioactive atoms, the author describes how this transmutation is technically obtained, indicates the two main families of atoms present in a used nuclear fuel and for which transmutation is to be investigated (long-lived fission residues or products, and transuranium elements) and of which the behaviour in neutron fluxes must be explored. He discusses the industrial means required for artificial transmutation. He discusses the interest of performing such a transmutation

Attenuated total reflectance-FT-IR spectroscopy for gunshot residue analysis: potential for ammunition determination.

Science.gov (United States)

Bueno, Justin; Sikirzhytski, Vitali; Lednev, Igor K

2013-08-06

The ability to link a suspect to a particular shooting incident is a principal task for many forensic investigators. Here, we attempt to achieve this goal by analysis of gunshot residue (GSR) through the use of attenuated total reflectance (ATR) Fourier transform infrared spectroscopy (FT-IR) combined with statistical analysis. The firearm discharge process is analogous to a complex chemical process. Therefore, the products of this process (GSR) will vary based upon numerous factors, including the specific combination of the firearm and ammunition which was discharged. Differentiation of FT-IR data, collected from GSR particles originating from three different firearm-ammunition combinations (0.38 in., 0.40 in., and 9 mm calibers), was achieved using projection to latent structures discriminant analysis (PLS-DA). The technique was cross (leave-one-out), both internally and externally, validated. External validation was achieved via assignment (caliber identification) of unknown FT-IR spectra from unknown GSR particles. The results demonstrate great potential for ATR-FT-IR spectroscopic analysis of GSR for forensic purposes.

Exposure of the Public from Large Deposits of Mineral Residues

International Nuclear Information System (INIS)

2011-06-01

All minerals and raw materials contain radionuclides of natural origin. In most situations, the exposure of humans to such radionuclides is considered to be part of the normal natural radiation background and is not generally of concern. In some cases, however, the radionuclide concentrations are elevated above normal levels or become elevated as a result of mineral processing activities, and measures for protecting against exposure to the material involved may need to be considered. The mineral or raw material is then treated as radioactive material for the purposes of radiation protection and falls within the definition of naturally occurring radioactive material (NORM). The IAEA has developed criteria for determining which materials need to be considered for regulatory control. For materials containing only radionuclides of natural origin, the criteria are an activity concentration of 1 Bq/g for 238 U, 235 U, 232 Th and their decay progeny and an activity concentration of 10 Bq/g for 40 K. These values were determined on the basis of the activity concentrations of these radionuclides in normal rocks and soil, and represent the (rounded) upper bounds of the ranges of such concentrations as determined by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). The values are intended to apply to all solid materials except foodstuffs, material in transport and radioactive residues in the environment (for which separate criteria apply) and 40 K in the body (which is excluded entirely from regulatory requirements). While the radiation dose was not a consideration in the determination of the above-mentioned regulatory criteria, the IAEA has noted that doses received by individuals as a consequence of the use of these criteria are unlikely to exceed about 1 mSv in a year, excluding the emanation of radon. However, in the case of bulk volumes of material contaminating water pathways, such as large deposits of NORM residues from mining and

Method of processing radioactive nuclide-containing liquids

International Nuclear Information System (INIS)

Hirai, Masahide; Tomoshige, Shozo; Kondo, Kozo; Suzuki, Kazunori; Todo, Fukuzo; Yamanaka, Akihiro.

1985-01-01

Purpose: To solidify radioactive nuclides in to a much compact state and facilitate the storage. Method: Liquid wastes such as drain liquids generated from a nuclear power plant at a low density of 1 x 10 -6 - 10 -4 μCi/ml are previously brought into contact with a chelate type ion exchange resin such as of phenolic resin or ion exchange resin to adsorb the radioactive nuclides on the resin and the nuclides are eluted with sulfuric acid or the like to obtain liquid concentrates. The liquid concentrates are electrolyzed in an ordinary electrolytic facility using platinum or the like as the anode, Al or the like as the cathode, under the presence of 1 - 20 g/l of non-radioactive heavy metals such as Co and Ni in the liquid and while adjusting pH to 2 - 8. The electrolysis liquid residue is returned again to the electrolysis tank as it is or in the form of precipitates coagulated with a polymeric floculant. The supernatant liquid upon floculating treatment is processed with the chelate type ion exchange resin into hazardless liquid. (Sekiya, K.)

Radioactive slurry waste treatment (2) - surfactants dose effects on filtration

International Nuclear Information System (INIS)

Jung, K. H.; Park, S. K.; Jung, W. S.; Baek, S. T.; Jung, K. J.

1999-01-01

The influence of anionic flocculants on the dewatering of radioactive slurries has been investigated in a laboratory-scale vacuum filtration unit. Simultaneously the influence of certain surfactants has also been investigated. Test results show that the flocculated filter cake generally contains higher residual water than the unflocculated cake. The non-ionic surfactant was effective in reducing the moisture content of the cake

Criteria and measurement techniques applicable to residual radioactivity on a decommissioned reactor site

International Nuclear Information System (INIS)

Woollam, P.B.

1988-12-01

This document summarises the radiological criteria which might be developed to cover the release of a partly decommissioned nuclear reactor site, then looks at the techniques available by which the site could be monitored to assure compliance with these criteria. In particular, the implications of existing levels of radioactive contamination resulting from airburst nuclear weapons tests and the Chernobyl accident are discussed. (author)

The radioactive organic wastewater treatment of INER

International Nuclear Information System (INIS)

Shen Chinchang; Chen Chaorui; Chung Jenchren

2014-01-01

The treatment strategy of radioactive organic wastewater was to separate it at first, then to treat it step by step by the characteristics of liquid layer. The waste liquid has separated into three layers, the organic layer, aqueous layer and the bottom gel mastic by natural sedimentation. The organic layer has occupied 23% of the total volume, the intermediate aqueous layer occupied 75% of the total volume, the bottom mastic was about 2% of the total. The aqueous layer of organic waste was with Total Organic Carbon (TOC) 20,000ppm. The combustion test shows good treatment performance and all samples can be decomposed completely by incineration. The experiment of incineration has passed the test more than 200 batches and 3000L low-level radioactive organic aqueous solution. The process goes smoothly and gas emission values far below the regulatory limit. Each kilogram of polymer absorber can absorb 45 kg aqueous solution to form a solid combustible material and can be decomposed by incineration. Organic waste solvents were diesel miscible and similar calorific value and small viscosity. It can be used as an incinerator auxiliary fuel of radioactive incinerator. The method testing has begun in this year. It has expected to save diesel fuel consumption of incineration, and well solved such kind waste liquid. (author)

Induced radioactivity in a 4 MW target and its surroundings

CERN Document Server

Agosteo, Stefano; Otto, Thomas; Silari, Marco

2003-01-01

An important aspect of a future CERN Neutrino Factory is the material activation arising from a 2.2 GeV, 4 MW proton beam striking a mercury target. An estimation of the hadronic inelastic interactions and the production of residual nuclei in the target, the magnetic horn, the decay tunnel, the surrounding rock and a downstream dump was performed by the Monte Carlo hadronic cascade code FLUKA. The aim was both to assess the dose equivalent rate to be expected during maintenance work and to evaluate the amount of residual radioactivity, which will have to be disposed of after the facility has ceased operation.

Predicting induced radioactivity for the accelerator operations at the Taiwan Photon Source.

Science.gov (United States)

Sheu, R J; Jiang, S H

2010-12-01

This study investigates the characteristics of induced radioactivity due to the operations of a 3-GeV electron accelerator at the Taiwan Photon Source (TPS). According to the beam loss analysis, the authors set two representative irradiation conditions for the activation analysis. The FLUKA Monte Carlo code has been used to predict the isotope inventories, residual activities, and remanent dose rates as a function of time. The calculation model itself is simple but conservative for the evaluation of induced radioactivity in a light source facility. This study highlights the importance of beam loss scenarios and demonstrates the great advantage of using FLUKA in comparing the predicted radioactivity with corresponding regulatory limits. The calculated results lead to the conclusion that, due to fairly low electron consumption, the radioactivity induced in the accelerator components and surrounding concrete walls of the TPS is rather moderate and manageable, while the possible activation of air and cooling water in the tunnel and their environmental releases are negligible.

Radioactive tracer profiling system and apparatus

International Nuclear Information System (INIS)

Wiley, R.; Veach, L.

1977-01-01

A radioactive charge is ejected into the borehole and a subsurface unit including a radiation detector is moved upwardly through this charge a number of times. The total radiation count as the unit moves up through the charge is obtained by integrating the output of the radiation detector during the period when the counter output exceeds the background radiation. The integrated count is displayed on a digital display unit. Compensation is provided for background radiation within the borehole. Also correction is made for the dead time of the radiation detector so that an accurate indication of the total amount of radioactivity remaining in the borehole during successive runs is obtained. 22 claims, 6 figures

Investigation of the environmental radioactivity around the mooring port

International Nuclear Information System (INIS)

Tanigawa, Yoshio

1976-01-01

Here are the main data for radioactivity examination performed in 1975 at Mutsu port, the mooring port of atomic energy vessel ''Mutsu''. No abnormality were observed in space γ ray dose ratio, and integrated doses measured by the thermofluorescence dosimeter at three monitoring posts in the port (G M tube) and three monitoring station in Mutsu City. A serial measurement of radioactivity concentration in sea water did not show any abnormality, either. Samples were taken from the surface soil of the ground, the bottom of the rivers, river water, drinking water, and milk and measured the total radioactivity by a gas flow counter. The measurement of the total β-radioactivity and radio nuclides analysis were carried out in sea water, the soil from the bottom of the sea and sea products. Abnormality considered to be caused by ''Mutsu'' did not observed at all. (Kobatake, H.)

Safety aspects of targets for ADTT: Activity, volatile products, residual heat release

International Nuclear Information System (INIS)

Gai, E.V.; Ignatyuk, A.V.; Lunev, V.P.; Shubin, Yu.N.

1999-01-01

Safety aspects of heavy metal liquid targets for the accelerator driven systems connected with the activity accumulation and residual energy release due to the irradiation with high energy proton beam are discussed. The results obtained for the lead-bismuth target that are under construction in IPPE now in the frame of ISTC Project No. 559 are briefly presented. The calculations and the analysis of the accumulation of the spallation reaction products, activity and energy release at various moments after the accelerator shutdown are presented. The concentrations of the reaction products, the total and partial activities, the activities of volatile products are determined. The contributions of the short-lived nuclides important for the prediction of the facility behaviour in regimes with the accelerator beam trips. The calculations and analysis of the residual energy release due to different decay type have been performed. The conclusions are as follows. The obtained results showed that long lived radioactivity accumulates mainly due to primary nuclear reactions. Secondary reactions are responsible for the production of small number of long-lived isotopes Bi-207, Po-210 and some others, being generated by radiative capture of low energy neutrons. It is possible to make a conclusion that neutrons in the energy range 20 - 800 MeV and protons with energy above 100 MeV give main contribution to the total activity generation although these parts of spectra inside the target give comparatively small contribution to the total flux. The correct consideration of short-lived nuclides contribution is the main problem in the analysis of the target behaviour in the case of short accelerator shutdowns. They make the determining contribution to the both activity and the heat release at the first moments after the accelerator shutdown, creating the intermediate links and additional channels for the long-lived nuclides accumulation chains. The strong dependence of calculated

Natural Radioactivity of Thermal Springs in Croatia

International Nuclear Information System (INIS)

Marovic, G.; Sencar, J.; Cesar, D.

1998-01-01

The Republic of Croatia is rich in thermal and mineral springs, which are widely popular for medical therapy, tourism, recreation, rehabilitation and drinking. Considering the popularity of the spas and the habits of our population to use the beneficial effects of these springs it is of interest to estimate the radiation doses received by patients or tourists staying in the spas. In view of this, the Radiation Protection Unit of the Institute for Medical Research and Occupational Health in Zagreb has been engaged in a research programme dealing with the natural radioactivity concentration in the Croatian thermal and mineral waters. The aim of this paper was to estimate total natural radioactivity (Ra, Ra decay) in thermal and mineral waters from the several spas in Croatia. On basis of the obtained data the Ra and Ra activity ratio was calculated for each investigated spa. In this study possible effects of natural radioactivity were determined for each radionuclide using a derived concentration (DC) for a group of individuals for municipal drinking water supplies. Values exceeding DC represent radionuclide concentrations for radioactive waste. Total percentage ratio for each spring was also calculated. Since natural radioactivity in some spas exceeds DC value the practise of using these waters should be regularly estimated and monitored in order to avoid any possible health effects. (author)

Information by the German Federal Government. Environmental radioactivity and radiation exposure in 2010

International Nuclear Information System (INIS)

2010-01-01

The information by the German Federal Government on the environmental radioactivity and radiation exposure in 2010 includes five chapters. (I) Natural radiation exposure: radiation sources, contributions from cosmic radiation, contaminated construction materials, food and drinking water, and radon, evaluation of the different components of natural radiation exposure. (II) Civilization caused radiation exposure: nuclear power plants, research centers, nuclear fuel processing plants, other nuclear facilities (interim storage facilities, repositories); summarizing evaluation for nuclear facilities; environmental radioactivity due to mining; radioactive materials in research, technology and households; industrial and mining residues; fall-out as a consequence of the Chernobyl reactor accident and nuclear weapon testing. (III) Occupational radiation exposure: civil radiation sources, natural radiation sources, special events. (IV) Medical radiation exposure; X-ray diagnostics; nuclear medicine; radiotherapy using ionizing radiation; radiotherapy using open radioactive materials; evaluation of radiotherapy. (V) Non-ionizing radiation: electromagnetic fields; optical radiation; certification of solaria.

Synthesis of high specific active tritiated Leu-enkephalin in the leucine residue

Energy Technology Data Exchange (ETDEWEB)

Baba, S.; Hasegawa, H.; Shinohara, Y. (Tokyo Coll. of Pharmacy (Japan))

1989-12-01

Leu-enkephalin labelled with tritium in the Leu residue has been prepared. Synthesis of the precursor peptide, (4,5-dehydroLeu{sup 5}-)Leu-enkephalin, was carried out by solid phase synthesis using Fmoc amino acid derivatives. The peptide was tritiated catalytically yielding {sup 3}H-Leu-enkephalin with a specific radioactivity of 4.39 TBq/mmol. The distribution of tritium label was investigated by reversed-phase high performance liquid chromatography with a synchronized accumulating radioisotope detector following acidic and enzymatic hydrolysis, which confirmed that the tritium label was entirely located at the Leu residue. (author).

78 FR 7818 - Request To Amend a License To Export Radioactive Waste

Science.gov (United States)

2013-02-04

... NUCLEAR REGULATORY COMMISSION Request To Amend a License To Export Radioactive Waste Pursuant to... Class A radioactive secondary waste will waste imported in either be returned accordance with NRC... Recipient country application no.; docket No. Eastern Technologies, Inc.; Class A radioactive The total...

Effect of commercial processing procedures on 14C-LINDANE residues in corn oil

International Nuclear Information System (INIS)

Soliman, S.M.

2006-01-01

At blooming, maize plants were sprayed twice, 23 days apart, at a dose of 22 mg equivalent to 5 μCi/ plant. At post harvest, maize seeds had a radioactivity corresponding to 0.36% of the applied dose. The insecticide residues in crude oil, cake and methanolic extract were amounted to 8 % and 60 % 5 % , respectively, of original residues inside the seeds.The 14 C-activity in the crude oil could be reduced by commercial processes locally used for refining. The refined oil had a residue level of about 0.7 ppm mainly in the form of unchanged lindane in addition to a number of chloro phenols as main metabolites. Refining of corn oil fortified with 14 C-lindane led to a high reduction of 14 C-lindane (88%). The refined oil contained a residue consisting lindane and its chloro phenols

Outcomes analysis of radioactive iodine and total thyroidectomy for pediatric Graves' disease.

Science.gov (United States)

Cohen, Reuven Zev; Felner, Eric I; Heiss, Kurt F; Wyly, J Bradley; Muir, Andrew B

2016-03-01

The majority of pediatric patients with Graves' disease will ultimately require definitive therapy in the form of radioactive iodine (RAI) ablation or thyroidectomy. There are few studies that directly compare the efficacy and complication rates between RAI and thyroidectomy. We compared the relapse rate as well as the acute and long-term complications of RAI and total thyroidectomy among children and adolescents with Graves' disease treated at our center. Medical records from 81 children and adolescents with a diagnosis of Graves' disease who received definitive therapy over a 12-year period were reviewed. Fifty one patients received RAI and 30 patients underwent thyroidectomy. The relapse rate was not significantly different between RAI and thyroidectomy (12.1% vs. 0.0%, p=0.28). There were no acute or long-term complications in the RAI group, but there were eight cases of hypoparathyroidism (two transient and six permanent) in the thyroidectomy group. None of the patients developed a recurrent laryngeal nerve injury. RAI is a safe and effective option for treatment of children and adolescents with Graves' disease. In light of the rate of permanent hypoparathyroidism seen at our center with thyroidectomy and previously published long-term safety of RAI, we recommend RAI as the first line treatment for children and adolescents with Graves' disease. For those centers performing thyroidectomies, we recommend that each center select 1-2 high-volume pediatric surgeons to perform all thyroid procedures, allowing individuals to increases case volume and potentially decrease long-term complications of thyroidectomy.

Management on radioactive wastes

International Nuclear Information System (INIS)

Balu, K.; Bhatia, S.C.

1979-01-01

The basic philosophy governing the radioactive waste management activities in India is to concentrate and contain as much activity as possible and to discharge to the environment only such of these streams that have radioactive content much below the nationally and internationally accepted standards. The concept of ''Zero Release'' is also kept in view. At Tarapur, the effluents are discharged into coastal waters after the radioactivity of the effluents is brought down by a factor 100. The effluents fΩm Rajasthan reactors are discharged into a lake keeping their radioactivity well within permissible limits and a solar evaporation plant is being set up. The plant, when it becomes operational, will be a step towards the concept of ''Zero Release''. At Kalpakkam, the treated wastes are proposed to be diluted by circulating sea water and discharged away from the shore through a long pipe. At Narora, ion exchange followed by chemical precipitation is to be employed to treat effluents and solar evaporation process for total containment. Solid wastes are stored/dispsed in the concrete trenches, underground with the water proofing of external surfaces and the top of the trench is covered with concrete. Highly active wastes are stored/disposed in tile holes which are vaults made of steel-lined, reinforced concrete pipes. Gas cleaning, dilution and dispersion techniques are adopted to treat gaseous radioactive wastes. (M.G.B.)

Radioactive content in Portuguese wines (1951-1971)

International Nuclear Information System (INIS)

Brito, M.C.F.Q.

1975-01-01

In this work we describe some considerations about the importance of a wine control quality, concerning the radioactive content susceptible to enter in a human diet. Results of total beta activity measurements and determination of radionuclides such as 90 Sr, 137 Cs and Uranium and Thorium radioactive families were determined in Fundao country wines (crops from 1951 to 1968) and in recent wines from different provinces

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

Volume reduction and encapsulation process for water containing low-level radioactive waste

International Nuclear Information System (INIS)

Fox, D.W.; Miller, G.P.; Weech, M.E.

1984-01-01

Solutions or slurries of waste material in water are dewatered and encapsulated within a polymer for disposal, comprising the operations of removing water therefrom with azeotropic mixture evaporation and encasing the dewatered waste residue in an organic polymer. The method and system disclosed are especially useful for the safe disposal of radioactive waste

Map of calculated radioactivity of fission product, 3

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I: Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr), Vol. II: Maps of radioactivity of each nuclide (Nb - Sb), Vol. III: Maps of radioactivity of each nuclide (Te - Tm). (auth.)

Map of calculated radioactivity of fission product, (1)

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr) Vol. II Maps of radioactivity of each nuclide (Nb - Sb) Vol. III Maps of radioactivity of each nuclide (Te - Tm) (auth.)

Map of calculated radioactivity of fission product, 2

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I: Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr), Vol. II: Maps of radioactivity of each nuclide (Nb - Sb), Vol. III: Maps of radioactivity of each nuclide (Te - Tm). (auth.)

Sustainable System for Residual Hazards Management

International Nuclear Information System (INIS)

Kevin M. Kostelnik; James H. Clarke; Jerry L. Harbour

2004-01-01

Hazardous, radioactive and other toxic substances have routinely been generated and subsequently disposed of in the shallow subsurface throughout the world. Many of today's waste management techniques do not eliminate the problem, but rather only concentrate or contain the hazardous contaminants. Residual hazards result from the presence of hazardous and/or contaminated material that remains on-site following active operations or the completion of remedial actions. Residual hazards pose continued risk to humans and the environment and represent a significant and chronic problem that require continuous long-term management (i.e. >1000 years). To protect human health and safeguard the natural environment, a sustainable system is required for the proper management of residual hazards. A sustainable system for the management of residual hazards will require the integration of engineered, institutional and land-use controls to isolate residual contaminants and thus minimize the associated hazards. Engineered controls are physical modifications to the natural setting and ecosystem, including the site, facility, and/or the residual materials themselves, in order to reduce or eliminate the potential for exposure to contaminants of concern (COCs). Institutional controls are processes, instruments, and mechanisms designed to influence human behavior and activity. System failure can involve hazardous material escaping from the confinement because of system degradation (i.e., chronic or acute degradation) or by external intrusion of the biosphere into the contaminated material because of the loss of institutional control. An ongoing analysis of contemporary and historic sites suggests that the significance of the loss of institutional controls is a critical pathway because decisions made during the operations/remedial action phase, as well as decisions made throughout the residual hazards management period, are key to the long-term success of the prescribed system. In fact

A study on residues and degradation of 14C-phoxim in spring wheat plants and soil

International Nuclear Information System (INIS)

Zhu Shuxiu; Yin Lishang

1988-01-01

A potting experiment on residues and degradation of 14 C-phoxim in spring wheat plants and soil was conducted in 1984∼1986. Seed dressing or soil mixing and spraying with 14 C-phoxim had been done at sowing and seedling stage respectively. The radioactivities of samples were detected on the low background (3cpm) GM or Backman LS 7800 liquid scintillation counter. The transmission, dissociation and residues of 14 C-phoxim in spring wheat plants and soil were investigated. The amount of 14 C-phoxim residues in the grains was determined. The dissipation of the residues of 14 C-phoxim after the harvesting of spring wheat plants were discussed; the residues could be decomposed into 14 CO 2 , dissolved in evaporated liquid and throwed into air, or stored in soil

Categorization of In-use Radioactive Sealed Sources in Egypt

International Nuclear Information System (INIS)

Hasan, M.A.; Mohamed, Y.T.; El Haleim, K.A.

2006-01-01

Radioactive sealed sources have widespread applications in industry, medicine, research and education. While most sources are of relatively low activity, there are many of medium or very high activity. The mismanagement of high activity sources is responsible for most of the radiological accidents that result in loss of life or disabling injuries. Because of the variety of applications and activities of radioactive sources, a categorization system is necessary so that the controls that are applied to the sources are adequate with its radiological risk. The aim of this work is to use the international Atomic Energy Agency (IAEA) categorization system to provide a simple, logical system for grading radioactive sealed sources in Egypt. The categorizations of radioactive sealed sources are based on their potential to cause harm to human health. This study revealed that total of 1916 sources have been used in Egypt in the different applications with a total activity of 89400 Ci according to available data in October 2005. (authors)

Radioactive emission from thermal power plants

Energy Technology Data Exchange (ETDEWEB)

Okamoto, K [New South Wales Univ., Kensington (Australia). Dept. of Applied Mathematics

1981-07-01

Radioactive hazards of the emissions and wastes of thermal power plants arising from fuel impurities of uranium and thorium are discussed. The hazard due to radioactive emission is calculated for an average Australian bituminous coal which contains 2 ppm of U and 2.7 ppm of Th. When the dust removal efficiency of a coal-fired power plant is 99%, the radioactive hazard is greater than that of a nuclear reactor of the same electrical output. After 500 years the radioactive toxicity of the coal waste will be higher than that of fission products of a nuclear reactor and after 2,000 years it will exceed the toxicity of all the nuclear wastes including actinides. The results of a recent calculation are shown, according to which the radioactive hazard of a coal-fired power plant to the public is from several hundred to several tens of thousands of times higher than that of a total fuel cycle of plutonium. It is found that in some regions, such as Japan, the hazard due to /sup 210/Po through seafood could be considerable.

Radioactivity monitoring in Ireland of air, deposition and water 1982-1987

International Nuclear Information System (INIS)

Sequeira, S.; McRandall, M.; Hayden, E.; Cunningham, J.D.

1989-02-01

The Nuclear Energy Board in conjunction with the Meteorological Service undertakes an environmental radioactivity monitoring programme with the objective of determining levels of artificially produced radioactivity in the Irish environment. The levels of radioactivity in airbourne dust, total fallout samples, precipitation and drinking water are presented for 1982, 1983, 1984, 1985, 1986 and 1987

Tissue distribution and excretion of radioactivity following administration of 14C-labeled deoxynivalenol to White Leghorn hens

International Nuclear Information System (INIS)

Prelusky, D.B.; Hamilton, R.M.; Trenholm, H.L.; Miller, J.D.

1986-01-01

The disposition of [ 14 C]deoxynivalenol ([ 14 C]DON) administered to hens as either a single oral dose or consumed in spiked feed over a 6-day period was determined by tracing the specific radioactivity of tissues and excreta. Following a single intubated dose (2.2 mg [ 14 C]DON; 2.4 microCi/bird), the toxin was found to be poorly absorbed; peak plasma levels (2-2.5 hr post-treatment) accounted for less than 1% of the administered dose. Maximum tissue residues were measured at 3 hr in all tissues (liver, kidney, brain, heart, spleen, proventriculus, gizzard, small intestine) except for fat, muscle, and oviduct which occurred at 6 hr postdosing. Among the organs, the highest activities were measured in kidney, liver, and spleen; however, these levels were equal to less than 500 ng DON equivalents/g tissue, and declined quickly. Clearance of radioactivity from tissue had an average half-life of 16.83 +/- 8.2 hr (range 7.7-33.3 hr, depending on the tissue). Elimination of the labeled toxin in excreta occurred rapidly; recovery of radioactivity accounted for 78.6, 92.1, and 98.5% of the dose by 24, 48, and 72 hr, respectively. In continuously dosed birds fed 2.2 mg unlabeled DON for 6 days followed by 2.2 mg (1.5 microCi) [ 14 C]DON for 6 days, accumulation of radioactivity in tissues did not occur. Maximum residual levels, which occurred in the kidneys, were only 60 ng DON equivalents/g. Estimated level of residues contained in the edible tissues amounted to only 13-16 micrograms DON/1.5 kg hen

Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-08-01

The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA`s future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper. Refs, figs, tabs

Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

International Nuclear Information System (INIS)

1998-08-01

The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA's future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper

Radioactivity leakage monitoring system

International Nuclear Information System (INIS)

Nakajima, Takuichiro; Noguchi, Noboru.

1982-01-01

Purpose: To obtain a device for detecting the leakage ratio of a primary coolant by utilizing the variation in the radioactivity concentration in a reactor container when the coolant is leaked. Constitution: A measurement signal is produced from a radioactivity measuring instrument, and is continuously input to a malfunction discriminator. The discriminator inputs a measurement signal to a concentration variation discriminator when the malfunction is recognized and simultaneously inputs a measurement starting time from the inputting time to a concentration measuring instrument. On the other hand, reactor water radioactivity concentration data obtained by sampling the primary coolant is input to a concentration variation computing device. A comparator obtains the ratio of the measurement signal from the measuring instrument and the computed data signal from the computing device at the same time and hence the leakage rate, indicates the average leakage rate by averaging the leakage rate signals and also indicates the total leakage amount. (Yoshihara, H.)

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

Residual stress improving method for reactor structural component and residual stress improving device therefor

Energy Technology Data Exchange (ETDEWEB)

Enomoto, Kunio; Otaka, Masahiro; Kurosawa, Koichi; Saito, Hideyo; Tsujimura, Hiroshi; Tamai, Yasukata; Urashiro, Keiichi; Mochizuki, Masato

1996-09-03

The present invention is applied to a BWR type reactor, in which a high speed jetting flow incorporating cavities is collided against the surface of reactor structural components to form residual compression stresses on the surface layer of the reactor structural components thereby improving the stresses on the surface. Namely, a water jetting means is inserted into the reactor container filled with reactor water. Purified water is pressurized by a pump and introduced to the water jetting means. The purified water jetted from the water jetting means and entraining cavities is abutted against the surface of the reactor structural components. With such procedures, since the purified water is introduced to the water jetting means by the pump, the pump is free from contamination of radioactive materials. As a result, maintenance and inspection for the pump can be facilitated. Further, since the purified water injection flow entraining cavities is abutted against the surface of the reactor structural components being in contact with reactor water, residual compression stresses are exerted on the surface of the reactor structural components. As a result, occurrence of stress corrosion crackings of reactor structural components is suppressed. (I.S.)

Residual stress improving method for reactor structural component and residual stress improving device therefor

International Nuclear Information System (INIS)

Enomoto, Kunio; Otaka, Masahiro; Kurosawa, Koichi; Saito, Hideyo; Tsujimura, Hiroshi; Tamai, Yasukata; Urashiro, Keiichi; Mochizuki, Masato.

1996-01-01

The present invention is applied to a BWR type reactor, in which a high speed jetting flow incorporating cavities is collided against the surface of reactor structural components to form residual compression stresses on the surface layer of the reactor structural components thereby improving the stresses on the surface. Namely, a water jetting means is inserted into the reactor container filled with reactor water. Purified water is pressurized by a pump and introduced to the water jetting means. The purified water jetted from the water jetting means and entraining cavities is abutted against the surface of the reactor structural components. With such procedures, since the purified water is introduced to the water jetting means by the pump, the pump is free from contamination of radioactive materials. As a result, maintenance and inspection for the pump can be facilitated. Further, since the purified water injection flow entraining cavities is abutted against the surface of the reactor structural components being in contact with reactor water, residual compression stresses are exerted on the surface of the reactor structural components. As a result, occurrence of stress corrosion crackings of reactor structural components is suppressed. (I.S.)

Plasma separation process: Disposal of PSP radioactive wastes

International Nuclear Information System (INIS)

1989-07-01

Radioactive wastes, in the form of natural uranium contaminated scrap hardware and residual materials from decontamination operations, were generated in the PSP facilities in buildings R1 and 106. Based on evaluation of the characteristics of these wastes and the applicable regulations, the various options for the processing and disposal of PSP radioactive wastes were investigated and recommended procedures were developed. The essential features of waste processing included: (1) the solidification of all liquid wastes prior to shipment; (2) cutting of scrap hardware to fit 55-gallon drums and use of inerting agents (diatomaceous earth) to eliminate pyrophoric hazards; and (3) compaction of soft wastes. All PSP radioactive wastes were shipped to the Hanford Site for disposal. As part of the waste disposal process, a detailed plan was formulated for handling and tracking of PSP radioactive wastes, from the point of generation through shipping. In addition, a waste minimization program was implemented to reduce the waste volume or quantity. Included in this document are discussions of the applicable regulations, the types of PSP wastes, the selection of the preferred waste disposal approach and disposal site, the analysis and classification of PSP wastes, the processing and ultimate disposition of PSP wastes, the handling and tracking of PSP wastes, and the implementation of the PSP waste minimization program. 9 refs., 1 fig., 8 tabs

Extraction and analysis of 14C-carbofuran radioactivity in soil sample

International Nuclear Information System (INIS)

Maizatul Akmam Mhd Nasir; Nashriyah Mat

2005-01-01

Carbofuran insecticide or nematicide sprayed onto soil in the agroecosystem will be taken up by plant. Carbofuran residue will pollute the environment and organisms in the food chain. Extraction and analysis of 14 C-carbofuran in soil from lysimeter were carried out. The Liquid Scintillation Counter (LSC) was used to measure radioactivity of 14 C-carbofuran in soil sample. (Author)

Penentuan Anomali Gayaberat Regional dan Residual Menggunakan Filter Gaussian Daerah Mamuju Sulawesi Barat

Directory of Open Access Journals (Sweden)

Adhika Junara Karunianto

2017-11-01

Full Text Available Gravity method is a geophysical method that has been frequently used in prospecting mineral resources. The parameter of searched object is based on variations of gravity acceleration measurements on the surface due to variations in sub-surface geological changes. Research area is located in Mamuju Area of West Sulawesi Province where tectonically a complex geological region, which is at a meeting of three large plates, the Pacific plate, the Indo-Australian plate and the Eurasian plate and the smaller Philippine plate. In addition, Mamuju is an area with a high radioactivity dose rate that has potency to radioactive minerals resources. The purpose of the research is to obtain gravity anomalies by using qualitative separation and interpretation of regional and residual gravity anomalies. Complete Bouguer Anomaly (CBA value of the research area obtained from the measurements was 46.0 – 115.7 mGal. Based on the CBA map, the separation process of regional gravity anomalies and residual using Gaussian filtering technique conducted. This filtering technique works based on spectral analysis of gravity amplitude changes in spatial where the result is a cutoff wave number of 1.1736 x 10-3/meter and a wavelength of 5373.45 m. The regional and residual gravity anomalies range from 51.8 to 102 mGal and -10.4 to 14.8 mGal respectively. The depth of influence of each anomaly is calculated based on their spectral wavelengths, resulting 970.97 m and 100.21 m for regional and residual anomalies respectively. There are five zones based on the residual anomaly map, which are zones A, B, C, D and E. The heaviest positive gravity anomaly is found in zone A and B, which is predicted to be influenced by Adang lava with relative north – south distribution.

Development of radioactive source scanner based on PLC

International Nuclear Information System (INIS)

Yang Guogui; Gao Xiang; Guo Hongli

2013-01-01

The radioactive radial uniformity of 68 Ge line radioactive sources is a critical quality parameter. The radioactive source scanner with linear scanning function is developed by making use of high-speed pulse counters, high-speed pulse output ports, and the powerful instruction system of Siemens S7-200 series programmable logic controller (PLC). A computer used as a host computer of the instrument communicate with. the PLC by point to point interface (PPI) protocol, The instrument with functions of data collection, transmission, displaying, saving, motion control and instrument parameter settings, can be used to measure the radioactive radial uniformity and total activity of line radioactive source. The advantages of Using the PLC to develop nuclear instrumentation are development speed, strong anti-interference ability, and low-cost. This paper mainly describes the control system implementation and feature of the instrument. (authors)

Uptake of endogenous and exogenous 226Ra by vegetables from soils of a highly radioactive region

International Nuclear Information System (INIS)

Lima, V.T.; Penna-Franca, E.

1988-01-01

The Pocos de Caldas Plateau is a weathered alkaline igneous intrusion where several radioactive anomalies (U and Th series) exist. Not only the local soils but also the edible vegetables produced in the region can present 226 Ra concentrations up to 10 times higher than those from areas of normal radioactivity. The aim of this work is to evaluate through greenhouse experiments, the uptake of endogenous and exogenous 226 Ra by carrots, brown beans and kale grown from four paired local natural and contaminated farm soils. Simultaneously, sequential selective extractions were performed to estimate the partitioning of 226 Ra among six geochemical fractions. The results showed that concentration ratios (CRs), related to plant dry weight, for endogenous and exogenous 226 Ra in soils, were of the order of 10 -2 -10 -1 and 10 -2 -10 0 respectively. The averages of 226 Ra exchangeable and residual fractions in soils were: 3.2% and 50.2% for endogenous and 15.4% and 6.0% for exogenous radium. The CRs calculated either in relation to total 226 Ra or to the exchangeable fraction in soils showed about the same variability. (author)

77 FR 52073 - Request To Amend a License To Export Radioactive Waste

Science.gov (United States)

2012-08-28

... NUCLEAR REGULATORY COMMISSION Request To Amend a License To Export Radioactive Waste Pursuant to..., 2012, July 31, 2012, XW012/ radioactive total of 5,500 materials and/or 02, 11005699. waste including tons or about radioactive various 1,000 tons waste that is materials (e.g., metal, 4,000 attributed to...

Experimental and theoretical study of the yields of residual product nuclei produced in thin targets irradiated by 100-2600 MeV protons

CERN Document Server

Titarenko, Y E; Karpikhin, E I

2003-01-01

The objective of the project is measurements and computer simulations of independent and cumulative yields of residual product nuclei in thin targets relevant as target materials and structure materials for hybrid accelerator-driven systems coupled to high-energy proton accelerators. The yields of residual product nuclei are of great importance when estimating such basic radiation-technology characteristics of hybrid facility targets as the total target activity, target 'poisoning', buildup of long-lived nuclides that, in turn, are to be transmuted, product nuclide (Po) alpha-activity, content of low-pressure evaporated nuclides (Hg), content of chemically-active nuclides that spoil drastically the corrosion resistance of the facility structure materials, etc. In view of the above, radioactive product nuclide yields from targets and structure materials were determined by an experiment using the ITEP U-10 proton accelerator in 51 irradiation runs for different thin targets: sup 1 sup 8 sup 2 sup , sup 1 sup 8 ...

Naturally occurring radioactive materials in construction integrating radiation protection in Reuse

CERN Document Server

Schroeyers, Wouter

2017-01-01

Naturally Occurring Radioactive Materials in Construction (COST Action NORM4Building) discusses the depletion of energy resources and raw materials and its huge impact not only on the building market, but also in the development of new synthetic building materials, whereby the reuse of various (waste) residue streams becomes a necessity. It is based on the outcome of COST Action TU 1301, where scientists, regulators, and representatives from industry have come together to present new findings, sharing knowledge, experiences, and technologies to stimulate research on the reuse of residues containing enhanced concentrates of natural radionuclides (NORM) in tailor-made building materials. Chapters address legislative issues, measurement, and assessment of building materials, physical and chemical aspects, from raw materials, to residues with enhanced concentrations of natural radionuclides (NORM), processes, building products containing NORM, and end-of-life and reuse requirements. Presents a holistic app...

Proceedings of a specialist meeting on regulatory approaches for the control of environmental residues containing naturally occurring radioactive material. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

Naturally occurring radionuclides are present in most material. The most common naturally occurring radionuclides in material are those of the uranium and thorium series and potassium-40. This material is commonly referred to as Naturally Occurring Radioactive Material (NORM). In some material the levels of naturally occurring radionuclides are significantly higher, to the extent that regulatory control may be required for radiation protection purposes. Regulation of NORM presents a range of new challenges for both regulators and operators. Unlike more traditional industries dealing with radionuclides, NORM industries have generally not had any radiological oversight and, for example, are not equipped for radiological monitoring. Some consumer goods containing NORM, which have not traditionally been considered as a radiological problem (such as some fertilizers), may require regulation and this may have social and economic consequences. The transport and disposal of NORM are also a concern, particularly due to the large volumes, which may need to be considered. For the majority of NORM, disposal has been by conventional means in the same way as for non-hazardous waste with no specific attention to radiological aspects. In some cases, there may be a need for intervention into existing NORM disposal sites. The International Commission on Radiological Protection (ICRP) published ICRP No. 82, Protection of the Public in Situations of Prolonged Radiation Exposure in 2000. This document provides guidance on managing residues, such as those arising from NORM industries, with potential impact on the public. However, with NORM residual waste there may be three different situations: residual waste created as the result of a past practice, residual waste created by an ongoing practice and waste which will arise from future activities. Regulation of NORM may therefore be consistent with consideration of a practice, an intervention or a combination of both. Different regulatory

Proceedings of a specialist meeting on regulatory approaches for the control of environmental residues containing naturally occurring radioactive material. Working material

International Nuclear Information System (INIS)

2005-01-01

Naturally occurring radionuclides are present in most material. The most common naturally occurring radionuclides in material are those of the uranium and thorium series and potassium-40. This material is commonly referred to as Naturally Occurring Radioactive Material (NORM). In some material the levels of naturally occurring radionuclides are significantly higher, to the extent that regulatory control may be required for radiation protection purposes. Regulation of NORM presents a range of new challenges for both regulators and operators. Unlike more traditional industries dealing with radionuclides, NORM industries have generally not had any radiological oversight and, for example, are not equipped for radiological monitoring. Some consumer goods containing NORM, which have not traditionally been considered as a radiological problem (such as some fertilizers), may require regulation and this may have social and economic consequences. The transport and disposal of NORM are also a concern, particularly due to the large volumes, which may need to be considered. For the majority of NORM, disposal has been by conventional means in the same way as for non-hazardous waste with no specific attention to radiological aspects. In some cases, there may be a need for intervention into existing NORM disposal sites. The International Commission on Radiological Protection (ICRP) published ICRP No. 82, Protection of the Public in Situations of Prolonged Radiation Exposure in 2000. This document provides guidance on managing residues, such as those arising from NORM industries, with potential impact on the public. However, with NORM residual waste there may be three different situations: residual waste created as the result of a past practice, residual waste created by an ongoing practice and waste which will arise from future activities. Regulation of NORM may therefore be consistent with consideration of a practice, an intervention or a combination of both. Different regulatory

Bolus injections of measured amounts of radioactivity

International Nuclear Information System (INIS)

Wesolowski, C.A.; Hogendoorn, P.; Vandierendonck, R.; Driedger, A.A.

1988-01-01

Many time-based radionuclide techniques, such as glomerular filtration rate measurement (GFR), require prompt intravenous delivery of and accurately measured tracer bolus with minimal residual tracer retention at the injection site. The quality assurance aspects of two antecubital vein, quantitative injection techniques were investigated. A flush bolus technique using a tuberculin syringe piggybacked onto a 10-ml saline flush was compared to a single blood pressure cuff injection technique. Scintillation camera data for each technique were compared for bolus duration in the abdominal aorta and for residual activity at the injection site at 5 min. Bolus times were measured as the FWHM of the gamma variate fit to the abdominal aortic regional time-activity curves. Relatively little focal activity was seen in the antecubital injection site following the flush bolus: marked residual activity was seen following the blood pressure cuff injections. The injection site/arm background ratios averaged 1.3 for the flush bolus and 30.1 for the cuff technique. Although both methods allowed accurate in vitro determination of administered radioactivity, only the tuberculin syringe flush bolus technique was acceptable for time-based quantitation because of its superior in vivo characteristics

Radioactivity of tap water in the Republic of Croatia

International Nuclear Information System (INIS)

Cesar, D.; Maracic, M.; Franic, Z.; Kovac, J.

1994-01-01

The purpose of the paper was to establish the difference between radioactivity level measured in tap water in relation to maximum permissible concentrations determined by law in the Republic of Croatia. Tables 1 and 2 give percentages of total beta activity in tap water of several cities in Croatia and Table 3 of 137 Cs, 3 H and 90 Sr specific activities, in relation to permissible levels. On basis of these data it could be concluded that total beta activity has exponentially decreased over the past 30 years and radioactivity in tape water of Croatia has never exceeded permissible levels. Taking in account possible hazards to human health that might be caused by the presence of radioactivity in water, this kind of investigation should be continued also in the future

Criteria and Processes for the Certification of Non-Radioactive Hazardous and Non-Hazardous Wastes

International Nuclear Information System (INIS)

Dominick, J.

2008-01-01

This document details Lawrence Livermore National Laboratory's (LLNL) criteria and processes for determining if potentially volumetrically contaminated or potentially surface contaminated wastes are to be managed as material containing residual radioactivity or as non-radioactive. This document updates and replaces UCRL-AR-109662, Criteria and Procedures for the Certification of Nonradioactive Hazardous Waste (Reference 1), also known as 'The Moratorium', and follows the guidance found in the U.S. Department of Energy (DOE) document, Performance Objective for Certification of Non-Radioactive Hazardous Waste (Reference 2). The 1992 Moratorium document (UCRL-AR-109662) is three volumes and 703 pages. The first volume provides an overview of the certification process and lists the key radioanalytical methods and their associated Limits of Sensitivities. Volumes Two and Three contain supporting documents and include over 30 operating procedures, QA plans, training documents and organizational charts that describe the hazardous and radioactive waste management system in place in 1992. This current document is intended to update the previous Moratorium documents and to serve as the top-tier LLNL institutional Moratorium document. The 1992 Moratorium document was restricted to certification of Resource Conservation and Recovery Act (RCRA), State and Toxic Substances Control Act (TSCA) hazardous waste from Radioactive Material Management Areas (RMMA). This still remains the primary focus of the Moratorium; however, this document increases the scope to allow use of this methodology to certify other LLNL wastes and materials destined for off-site disposal, transfer, and re-use including non-hazardous wastes and wastes generated outside of RMMAs with the potential for DOE added radioactivity. The LLNL organization that authorizes off-site transfer/disposal of a material or waste stream is responsible for implementing the requirements of this document. The LLNL Radioactive and

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

Nuclide radioactive decay data uncertainties library

International Nuclear Information System (INIS)

Barabanova, D S; Zherdev, G M

2017-01-01

The results of the developing the library of uncertainties of radioactive decay data in the ABBN data library format are described. Different evaluations of uncertainties were compared and their effects on the results of calculations of residual energy release were determined using the test problems and experiment. Tables were generated in the ABBN format with the data obtained on the basis of libraries in ENDF-6 format. 3821 isotopes from the ENDF/B-7 data library, 3852 isotopes from the JEFF-3.11 data library and 1264 isotopes from the JENDL-4.0 data library were processed. It was revealed that the differences in the evaluations accepted in different decay data libraries are not so big, although they sometimes exceed the uncertainties assigned to the data in the ENDF/B-7 and JEFF-3.11 libraries, which as a rule, they agree with each other. On the basis of developed method it is supposed to create a library of data uncertainties for radioactive decay within the constant data system in FSUE RFNC-VNIIEF with its further connection with CRYSTAL module. (paper)

Radioactive waste management practices in India

International Nuclear Information System (INIS)

Kaushik, C.P.

2016-01-01

Nuclear technologies are used for generation of electricity and for production of a wide range of radionuclides for use in research and development, health care and industry. One of the special features of nuclear industry is that it uses nuclear fission as source of energy. As a result, a large amount of energy is available from relatively small amount of fuel. The resultant quantities of waste are relatively very small in case of nuclear power as compared to same for conventional thermal power stations. In India, 'closed fuel cycle' has been adopted treating spent nuclear fuel as a material of resource. The closed fuel cycle aims at recovery and recycle of U and Pu, separation of useful isotopes of Cs and Sr for use in health care and industry. This finally leads to a very small percentage of residual material present in spent nuclear fuel requiring their management as radioactive waste. Another special feature of the Indian Atomic Energy Programme is the attention paid from the very beginning to the safe management of radioactive waste

Labelled compounds for agrochemical residue studies in developing countries

International Nuclear Information System (INIS)

1977-01-01

Potential applications of stable and radioactive isotopic tracers for assessing undesirable contaminants in agriculture, fisheries and food are discussed as related to developing countries. Sources and types of residues are considered, and their local implications; also, the availability of suitably labelled compounds, including possible international cooperation to facilitate more centralized and economic preparation, and the distribution of labelled intermediates and compounds for use by local scientists. The provision of training courses and their syllabus are reviewed. Experience in the Joint FAO/IAEA chemical residue and pollution programme has indicated a need for longer-lived radioisotopically labelled pesticides (insecticides, acaricides, fungicides, herbicides, fumigants, etc.) for studying their behaviour. 15 N-, 13 C- or 2 H-labelled fertilizers and fertilizer additives such as nitrification inhibitors will shortly be needed, for studying the behaviour of fertilizer nitrogen residues, and their regulation and conservation, under conditions prevailing in the developing countries. Compounds labelled with stable isotopes are considered particularly valuable under field conditions. The report reviews the present situation and presents specific recommendations to the Directors General of FAO and IAEA

Measuring arrangement for simultaneous and continuous determination of the total and radioactive amounts of reactive matters in flowing inert gases. Pt. 1

International Nuclear Information System (INIS)

Figge, K.; Martinen, H.; Schulz, W.

1976-01-01

In order to investigate the metabolism behaviour of radiocarbon-labelled substances, a special apparatus has been designed which enables a fully automatic as well as continuous and simultaneous determination of the total and the 14 C-labelled carbon dioxide (CO 2 ) in the respiratory air of small animals. The CO 2 which is exhaled by the experimental animals is absorbed quantitatively in a novel absorber-scintillator cocktail. The quantity of combined total CO 2 is then determined by measuring the specific conductivity whereas the amount of radioactive CO 2 is assessed via scintillation measurement. The measuring accuracy achieved is around 10 N cm 3 or about 5 nCi, whereas the CO 2 recovery is above 98%. In addition to the recording in a linear recorder, the data are transferred to punching tapes and can be evaluated in an EDP unit. (orig.) [de

Natural Radioactivity in Ceramic Materials

International Nuclear Information System (INIS)

Abu Khadra, S.A.; Kamel, N.H.

2005-01-01

Ceramics are one of the most important types of the industrial building materials. The raw materials of the ceramic are made of a mixture of clay, feldspar, silica, talc kaolin minerals together with zirconium silicates (ZrSiO4).The ceramic raw materials and the final products contain naturally occurring radionuclide mainly U-238 and, Th-232 series, and the radioactive isotope of potassium K-40. Six raw ceramic samples were obtained from the Aracemco Company at Egypt together with a floor tile sample (final product) for measuring radioactive concentration levels., The activity of the naturally U-238, Th-232, and K-40 were determined as (Bq/kg) using gamma spectroscopy (Hyperactive pure germanium detector). Concentration of U and Th were determined in (ppm) using spectrophotometer technique by Arsenazo 111 and Piridy l-Azo -Resorcinol (PAR) indicators. Sequential extraction tests were carried out in order to determine the quantity of the radionuclide associated with various fractions as exchangeable, carbonate, acid soluble and in the residue. The results evaluated were compared to the associated activity indices (AI) that were defined by former USSR and West Germany

Current status of radioactive waste management in Japan

International Nuclear Information System (INIS)

Amanuma, Tsuyoshi

1985-01-01

In Japan the nuclear power generation capacity now exceeds the level of 20,000 MW, 24.3 % of the total power generation. It constitutes the major position of energy source, a substitute for a petroleum. In the nuclear power, chemical engineering contributes significantly to treatment and disposal of the radioactive wastes. In the interim report by an ad hoc committee in the Atomic Energy Commission, for the future, rational grouping of the wastes and the direction of land disposal are stated. Contents are the following: basic ideas for the radioactive wastes, radioactive wastes countermeasures in Japan (wastes classification, low and high level and transuranic wastes), radioactive wastes in the nuclear fuel cycle (reactor and fuel reprocessing and reactor dismantling wastes). (Mori, K.)

Effects of food processing on the radioactivity of vegetables and cereals

International Nuclear Information System (INIS)

Roussel-Debet, S.; Real, J.

1995-01-01

The decrease of radioactivity for 134 Cs, 85 Sr, 106 Ru, 57 Co, 110m Ag during food processing was measured. Washing and bleaching vegetables directly contaminated by a single aerosol deposit led to a radioactivity decrease (depending on the vegetable, the radionuclide and the time of deposition) up to 90% for caesium. The efficiency of these processes was less important when the vegetables were contaminated by root transfer, except for peeling of root vegetables. Canning of vegetables indirectly contaminated by caesium, strontium, cobalt and ruthenium, after paring and bleaching, was rather interesting with residual radioactivity varying from 30 to 50% for green beans and from 5 to 20% for carrots. Measurements of stable caesium and strontium in cereals before and after industrial processing showed an important activity decrease; retention factors varied from 0.1 to 0.2 for wheat milling and 0.1 to 0.4 for rice processing. (authors). 6 refs., 9 tabs., 1 figs

Exposure to radiation through the residual activity of waste treated by conventional methods

International Nuclear Information System (INIS)

Deckert, A.; Hoppe, G.; John, T.; Thierfeldt, S.

1993-01-01

Data obtained by questionnaires provided information on the type, amount, nuclide vector and maximum permissible value of low-level radioactive residues that occur in nuclear installations of due to industrial, scientific and medical uses of radioactive materials and are officially released to be disposed of by conventional methods. The general legal background of waste disposal methods, in particular the official regulations surrounding the waste disposal law, were described. On this basis, parameters and maximum radioactive burdens were specifically defined for garbage dumps for refuse from private households and those for building rubbish. Investigations were carried out into exposure paths that may have a role in the radioactive doses taken up by personnel (inhalation) or the general population (ingestion) through contaminated water. The radiation dose attributable to those exposure paths were expressed in relation to a specific unit activity of waste (1 bq/G). A dose of 10 μ Sv/r was taken as a standard to define a threshold value for each individual nuclide released for conventional waste disposal. It appears reasonable that such values are determined for groups of nuclides. (HP) [de

The 2016-2018 National Plan of Management of Radioactive Materials and Wastes - Project

International Nuclear Information System (INIS)

Gazzo, Alexis; Robert, Jean-Gabriel; Abraham, Christophe; Benaze, Manon de

2015-01-01

A first document contains the project of the National Plan of Management of Radioactive Materials and Wastes (PNGMDR) for the period 2016-2018: principles and objectives (presentation of radioactive materials and wastes, principles to be taken into account to define pathways of management of radioactive wastes, legal and institutional framework, information transparency), the management of radioactive materials (context and challenges, management pathways, works on fast breeder reactors of fourth generation), assessment and perspectives of existing pathways of management of radioactive wastes (management of historical situations, management of residues of mining and sterile processing, management of waste with a high natural radioactivity, management of very short life waste, of very low activity wastes, and low and medium activity wastes), needs and perspectives regarding management processes to be implemented for the different types of radioactive wastes. Appendices to this document contain a recall of the content of previous PNGMDR since 2007, a synthesis of realisations and researches performed abroad, research orientations for the concerned period, and international agreement on spent fuel and radioactive waste management. A second document, released by the ASN, proposes an environmental and strategic assessment of the plan. A third one and a fourth one contain the opinion of the Environmental Authority, respectively on the plan preliminary focus, and on the plan itself. An answer to this last one is then proposed, followed by a synthesis of the plan project and the text of the corresponding decree

Treatment methods and comparative risks of thorium removal from waste residues

International Nuclear Information System (INIS)

Porter, R.D.; Hamby, D.M.; Martin, J.E.

1997-07-01

This study was done to examine the risks of remediation and the effectiveness of removal methods for thorium and its associated radioactive decay products from various soils and wastes associated with DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). Removal of 230 Th from uranium process residues would significantly reduce the buildup of 226 Ra (half-life of 1600 years), and since 230 Th concentrations at most of the important sites greatly exceed the 226 Ra concentrations, such removal would reduce the accumulation of additional radiation risks associated with 226 Ra and its products; and, if treatment also removed 226 Ra, these risks could be mitigated even further. Removal of 232 Th from thorium process residues would remove the source material for 228 Ra, and since 228 Ra has a half-life of 5.76 years, its control at FUSRAP sites could be done with land use controls for the 30--50 years required for 228 Ra and the risks associated with its decay products to decay away. It must be recognized, however, that treatment methods invariably require workers to process residues and waste materials usually with bulk handling techniques. These processes expose workers to the radioactivity in the materials, therefore, workers would incur radiological risks in addition to industrial accident risks. An important question is whether the potential reduction of future radiological risks to members of the public justifies the risks that are incurred by remediation workers due to handling materials. This study examines, first, the effectiveness of treatment and then the risks that would be associated with remediation

Determination of total alpha activity index in samples of radioactive wastes

International Nuclear Information System (INIS)

Galicia C, F. J.

2015-01-01

This study aimed to develop a methodology of preparation and quantification of samples containing radionuclides beta and/or alpha emitters, to determine the rates of alpha and beta total activity of radioactive waste samples. For this, a device of planchettes preparer was designed, to assist the planchettes preparation in a controlled environment and free of corrosive vapors. Planchettes were prepared in three means: nitrate, carbonate and sulfate, to different mass thickness, natural uranium (alpha and beta emitter) and in case of Sr-90 (beta emitter pure) only in half nitrate; and these planchettes were quantified in an alpha/beta counter, in order to construct the self-absorption curves for alpha and beta particles. These curves are necessary to determine the rate of alpha-beta activity of any sample because they provide the self-absorption correction factor to be applied in calculating the index. Samples with U were prepared with the help of the device of planchettes preparer and subsequently were analyzed in the proportional counter Mpc-100 Pic brand. Samples with Sr-90 were prepared without the device to see if there was a different behavior with respect to obtaining mass thickness. Similarly they were calcined and carried out count in the Mpc-100. To perform the count, first the parameters of counter operating were determined: operating voltages for alpha and beta particles 630 and 1500 V respectively, a count routine was generated where the time and count type were adjusted, and counting efficiencies for alpha and beta particles, with the aid of calibration sources of 210 Po for alphas and 90 Sr for betas. According to the results, the counts per minute will decrease as increasing the mass thickness of the sample (self-absorption curve), adjusting this behavior to an exponential function in all cases studied. The minor self-absorption of alpha and beta particles in the case of U was obtained in sulfate medium. The self-absorption curves of Sr-90 follow the

Determination of the probability for radioactive materials on properties in Monticello, Utah

International Nuclear Information System (INIS)

Wilson, M.J.; Crutcher, J.W.; Halford, D.K.

1991-01-01

The former uranium mill site at Monticello, Utah, is a surplus facility subject to clean-up under the Surplus Facilities Management Program (SFMP). Surrounding properties contaminated with mill site material are also subject to cleanup, and are referred to as Monticello Vicinity Properties (MVP). The Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory (ORNL), Grand Junction, Colorado (GJ), was directed by the US Department of Energy (DOE) in July 1988 to assess the radiological condition of properties in Monticello, Utah. Since the Monticello activities are on the National Priority List, extra measures to identify potentially contaminated properties were undertaken. Thus, the likelihood that a random property could contain radioactive materials became a concern to the DOE. The objective of this study was to determine the probability that a vicinity property not addressed under the MVP project could contain Monticello mill-related residual radioactive material in excess of the DOE guidelines. Results suggest approximately 20% of the properties in the Monticello area contain Monticello mill-related residual radioactive material in excess of the DOE guidelines. This suggested that further designation measures be taken prior to the close of the designation phase. A public relations effort that included a property-owner mailing effort, public posting, and newspaper advertisement was one measure taken to ensure that most properties were assessed. As a consequence of this study, DOE directed that radiological screening surveys be conducted on the entirety of the Monticello area

Long-term stable, long-term safe storage of residues and radioactive waste. Contribution to discussion to the storage (final storage); Langzeitstabile, langzeitsichere Verwahrung von Rueckstaenden und radioaktiven Abfaellen. Beitrag zur Diskussion um Lagerung (Endlagerung)

Energy Technology Data Exchange (ETDEWEB)

Lersow, Michael [DGGT e.V., Breitenbrunn/Erzgeb. (Germany). Ak 5.5 Tailings; Gellermann, Rainer [Nuclear Control and Consulting GmbH, Braunschweig (Germany)

2015-09-15

In this paper it is presented, where radioactive waste and residues occur, how these materials can be classified, which rules and regulations have to be complied with regarding the disposal and which geotechnical environmental constructions (final repositories) are suitable to guarantee a safe long-term disposal of these materials. Primary protection objective is ''to permanently prevent the transfer of toxic, radioactive contaminations into the biosphere by air, water or rock path or to keep the amount of contamination within a commonly accepted range''. Radionuclide inventories and the given time period considered for long-term safety are compared with. It is shown, that the site-specific disposal solutions cannot be justified by the radioactive inventory deposited there. The given period of 10{sup 6} years is critically evaluated. Based on this it is suggested to subdivide this period into two time periods with different prognosis reliabilities. Results of a specially designed long-term monitoring as part of the site-specific waste disposal solution should be considered for the long-term safety proof. A modular concept for the final storage of High Active Waste (HAW) is derived based on the critical evaluation of the long-term safety, including transmutation, provisional storage and monitoring module. A foundation model is proposed to guarantee the financial resources required for the disposal of HAW.

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

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

Radioactive waste management and disposal

International Nuclear Information System (INIS)

Simon, R.; Orlowski, S.

1980-01-01

The first European Community conference on Radioactive Waste Management and Disposal was held in Luxembourg, where twenty-five papers were presented by scientists involved in European Community contract studies and by members of the Commission's scientific staff. The following topics were covered: treatment and conditioning technology of solid intermediate level wastes, alpha-contaminated combustible wastes, gaseous wastes, hulls and dissolver residues and plutonium recovery; waste product evaluation which involves testing of solidified high level wastes and other waste products; engineering storage of vitrified high level wastes and gas storage; and geological disposal in salt, granite and clay formations which includes site characterization, conceptual repository design, waste/formation interactions, migration of radionuclides, safety analysis, mathematical modelling and risk assessment

Marking with radioactive iodine of a plasma substitute and preliminary essays of his kinetic behaviour in rats; Marcacao com radioiodo de um sucedaneo do plasma e ensaios preliminares de seu comportamento cinetico em ratos

Energy Technology Data Exchange (ETDEWEB)

Cova, Wilma Guimaraes

1973-07-01

A blood plasma substitute (Haem accel - PGO), which has as a base a degraded and polymerized gelatin, was labelled with radioactive iodine (I-131) and preliminary essays of its kinetic behavior was done. We have used the labelling method of McFarlaner. The results obtained - radiochemical yield and purity - were favorable. The kinetic behaviour the residual radioactivity studied by measuring the residual radioactivity of the body and excreta in groups of male Wistar rats for a maximum period of 150 hours. These results have shown and excellent correlation for a two components exponential function's adjustment, suggesting therefore a bi compartmental mathematical model. (author)

A Genetic Algorithm Approach to the Optimization of a Radioactive Waste Treatment System

International Nuclear Information System (INIS)

Yang, Yeongjin; Lee, Kunjai; Koh, Y.; Mun, J.H.; Kim, H.S.

1998-01-01

This study is concerned with the applications of goal programming and genetic algorithm techniques to the analysis of management and operational problems in the radioactive waste treatment system (RWTS). A typical RWTS is modeled and solved by goal program and genetic algorithm to study and resolve the effects of conflicting objectives such as cost, limitation of released radioactivity to the environment, equipment utilization and total treatable radioactive waste volume before discharge and disposal. The developed model is validated and verified using actual data obtained from the RWTS at Kyoto University in Japan. The solution by goal programming and genetic algorithm would show the optimal operation point which is to maximize the total treatable radioactive waste volume and minimize the released radioactivity of liquid waste even under the restricted resources. The comparison of two methods shows very similar results. (author)

Technology applications for radioactive waste minimization

International Nuclear Information System (INIS)

Devgun, J.S.

1994-01-01

The nuclear power industry has achieved one of the most successful examples of waste minimization. The annual volume of low-level radioactive waste shipped for disposal per reactor has decreased to approximately one-fifth the volume about a decade ago. In addition, the curie content of the total waste shipped for disposal has decreased. This paper will discuss the regulatory drivers and economic factors for waste minimization and describe the application of technologies for achieving waste minimization for low-level radioactive waste with examples from the nuclear power industry

Radioactive waste management

International Nuclear Information System (INIS)

Kizawa, Hideo

1982-01-01

A system of combining a calciner for concentrated radioactive liquid waste and an incinerator for miscellaneous radioactive solid waste is being developed. Both the calciner and the incinerator are operated by fluidized bed method. The system features the following points: (1) Inflammable miscellaneous solids and concentrated liquid can be treated in combination to reduce the volume. (2) Used ion-exchange resin can be incinerated. (3) The system is applicable even if any final waste disposal method is adopted; calcinated and incinerated solids obtained as intermediate products are easy to handle and store. (4) The system is readily compatible with other waste treatment systems to form optimal total system. The following matters are described: the principle of fluidized-bed furnaces, the objects of treatment, system constitution, the features of the calciner and incinerator, and the current status of development. (J.P.N.)

Radioactive waste management at Institute for Nuclear Research (ICN) - Pitesti

International Nuclear Information System (INIS)

Bujoreanu, C.

2004-01-01

The amounts of liquid and solid wastes accumulated at the Radioactive Wastes Treatment Plant are given. The technologies used for the treatment and conditioning of radioactive wastes are presented. The final product is metallic drum-concrete-radioactive wastes (type A package) for the final disposal at the National Repository Baita, Bihor. The facilities for radioactive waste management at ICN Pitesti are: Plant for treatment, with uranium recovery of liquid radioactive waste resulting from the fabrication of CANDU type nuclear fuel; Plant for treatment of low-active liquid wastes; Plant for conditioning in concrete of the radioactive concentrate obtained during the evaporation treatment of liquid radioactive waste; Plant for incineration of solid radioactive waste contaminated with natural uranium; Plant for treatment and conditioning of organic liquid radioactive waste with tritium content. This wastes are generated by Cernavoda-NPP operation; Plant for conditioning into bitumen of spent ion exchangers at TRIGA reactor. The existing Facility is Baita repository - with two rock cavities of an uranium mine and the total capacity of 21000 containers (200 l drums)

Radioactivity Monitoring of the Irish Environment 2006

International Nuclear Information System (INIS)

Smith, V.; Dowdall, A; Fegan, M.; Hayden, E.; Kelleher, K.; Long, S.; McEvoy, I.; Somerville, S.; Wong, J.; Pollard, D.

2007-10-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2006. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the environment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. Radioactivity is present in the environment due to natural processes, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England, which are licensed by the UK Environment Agency, continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2006 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at ten stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows concentrations of caesium-137 to be measured; another is equipped to detect the presence of the gas krypton-85. This gas is released into the environment primarily as a result of the

Method of disposing radioactive wastes

International Nuclear Information System (INIS)

Isozaki, Kei.

1983-01-01

Purpose : To enable safety ocean disposal of radioactive wastes by decreasing the leaching rate of radioactive nucleides, improving the quick-curing nature and increasing the durability. Method : A mixture comprising 2 - 20 parts by weight of alkali metal hydroxide and 100 parts by weight of finely powdered aqueous slags from a blast furnace is added to radioactive wastes to solidify them. In the case of medium or low level radioactive wastes, the solidification agent is added by 200 parts by weight to 100 parts by weight of the wastes and, in the case of high level wastes, the solidification agent is added in such an amount that the wastes occupy about 20% by weight in the total of the wastes and the solidification agent. Sodium hydroxide used as the alkali metal hydroxide is partially replaced with sodium carbonate, a water-reducing agent such as lignin sulfonate is added to improve the fluidity and suppress the leaching rate and the wastes are solidified in a drum can. In this way, corrosions of the vessel can be suppressed by the alkaline nature and the compression strength, heat stability and the like of the product also become excellent. (Sekiya, K.)

Radioactive waste disposal process geological structure for the waste disposal

International Nuclear Information System (INIS)

Courtois, G.; Jaouen, C.

1983-01-01

The process described here consists to carry out the two phases of storage operation (intermediate and definitive) of radioactive wastes (especially the vitrified ones) in a geological dispositif (horizontal shafts) at an adequate deepness but suitable for a natural convection ventilation with fresh air from the land surface and moved only with the calorific heat released by the burried radioactive wastes when the radioactive decay has reached the adequate level, the shafts are totally and definitely occluded [fr

The effect of commercial processing procedures on 14C-carbendazim residues in soybean oil and tomato

International Nuclear Information System (INIS)

Peng Genyuan; Wang Huaguo; Qi Mengwen; Wang Fujun; Zhou Changjiu

1994-01-01

Under simulated agricultural practices, soybean plants were treated with 14 C-labelled carbendazim during the blooming stage. The residue in seeds was determined to be 0.067 ppm; corresponding to 0.076 ppm respectively. After subjecting the oil to degumming, alkali treatment, bleaching and deodorization, 53.7% of original radioactivity was removed. Deodorization was the most effect process, removing about 20% of the residue. The concentration of residues in the deodorized oil decreased about 30%. In soybean seed and cake, the residue was mainly present as carbendazim, the concentration of the other metabolites did not exceed 30% of the residue. Tomatoes grown on a field plot were treated with 14 C-carbendazim. After harvest, the tomatoes were processed into tomato juice and canned whole fruit. The magnitude and nature of residues in samples taken at several processing steps were determined to evaluate the effect of commercial processing on removing or eliminating the residues. The results showed that the surface residues on tomato would be removed efficiently by simple washing of tomato. A buffer solution of phosphate had the highest efficiency. Tomato juice contained lower residues than canned whole fruit

Persistence of pirimiphos methyl residues in stored wheat

International Nuclear Information System (INIS)

Zennouche, B.; Bennaceur, M.

1991-03-01

The persistence of 14C pirimiphos methyl in stored wheat was investigated under local conditions during a storage period of 6 months. Surface, methanol extractable and bound residues were quantified. There was a gradual increase in the surface residues over the storage period. 27,97% of the applied amount was found in the surface residues and 54,16% in the extractable and bound residues one month after treatment. After 6 months storage, about 17,8% of the total quantity of the applied pirimiphos methyl remained on the surface and about 58,6% was present in the grains (extractable and bound residues). During cooking 10,91% of the extractable and bound residues were lost

Environmental radioactivity and radiation exposure

International Nuclear Information System (INIS)

1980-01-01

In 1977 population exposure in the Federal Republic of Germany has not changed as compared to the previous years. The main share of the total exposure, nearly two thirds, is attributed to natural radioactive substances and cosmic radiation. The largest part (around 85%) of the artificial radiation exposure is caused by X-ray diagnostics. In comparison to this, radiation exposure from application of ionizing radiation in medical therapy, use of radioactive material in research and technology, or from nuclear facilities is small. As in the years before, population exposure caused by nuclear power plants and other nuclear facilities is distinctly less than 1% of the natural radiation exposure. This is also true for the average radiation exposure within a radius of 3 km around nuclear facilities. On the whole, the report makes clear that the total amount of artificial population exposure will substantially decrease only if one succeeds in reducing the high contribution to the radiation exposure caused by medical measures. (orig.) [de

The role of wastes from nuclear power plants in the overall management of radioactive wastes

International Nuclear Information System (INIS)

Krause, H.

1983-01-01

The wastes arising from nuclear power plants (NPP) are rather low in activity and the radionuclides contained therein have a low radiotoxicity and short half-life as a rule. However, NPPs are the largest in number among all nuclear facilities and produce the greatest amount of radioactive wastes. All NPPs have been able to keep the radiation doses in the environment below the permissible values, in most cases at 1 mrem/a or even lower. The methods applied for the treatment of liquid radioactive effluents have reached a high degree of effectivity and reliability. For the solidification of the residues several appropriate methods are available. However, some improvements are still desirable. Although methods exist for incineration, cutting and baling of solid wastes, only the last method is employed at NPPs as a rule. Central treatment facilities could improve this situation. The exhaust air treatment has reached a state that satisfies high standards during normal operation and in design base accidents. Improvements seem indicated regarding the in situ-inspection of HEPA-filters and the protection of filters against excess humidity and droplets. The partial and total decommissioning of NPPs has already been demonstrated. The problems caused by the wastes arising from such actions are in the same range as those from routine operation and maintenance of NPPs. Large amounts of radioactive wastes have already been disposed of by shallow land burial, disposal into deep geological formations or dumping into the deep sea. Specific standards could probably facilitate the disposal of wastes from NPPs. The present management of radioactive wastes from NPPs satisfies all actual needs. Therefore, spectacular new developments are neither required nor to be expected. However, by the continuous improvement of details and by optimization of the whole system progress can still be achieved and useful contributions to the further development of nuclear energy be made. (author)

Method for reduction in volume and encapsulation of water-containing weakly radioactive waste

International Nuclear Information System (INIS)

Fox, D.W.; Miller, G.P.; Weech, M.E.

1982-01-01

Solutions and slurries of waste material in water are dehydrated and enclosed in a polymerizate for final storage. The water is removed as an azeotropic mixture and the dehydrated waste residue is then enclosed in an organic polymerizate. The method and system disclosed in this patent claim are particularly suitable for safe removal of radioactive waste. (orig.) [de

Treatment and immobilization of intermediate-level radioactive wastes

International Nuclear Information System (INIS)

Lerch, R.E.; Greenhalgh, W.O.; Partridge, J.A.; Richardson, G.L.

1979-01-01

A new program underway at the Hanford Engineering Development Laboratory (HEDL) to develop and demonstrate treatment and immobilization technologies for intermediate-level wastes (ILW) generated in the nuclear fuel cycle is discussed. ILW are defined as those liquid and solid radioactive wastes, other than high-level wastes and fuel cladding hulls, that in packaged form have radiation dose readings greater than 200 millirem/hr at the packaged surface and 10 millirem/hr at three feet from the surface. The IAEA value of 10 4 Ci/m 3 for ILW defines the upper limit. For comparative purposes, reference is also made to certain aspects of low-level radioactive wastes (LLW). Initial work has defined the sources, quantities and types of wastes which comprise ILW. Because of the wide differences in composition (e.g., acids, salt solutions, resins and zeolites, HEPA filters, etc.) the wastes may require different treatments, particularly those wastes containing volatile contaminants. The various types of ILW have been grouped into categories amenable to similar treatment. Laboratory studies are underway to define treatment technologies for liquid ILW which contain volatile contaminants and to define immobilization parameters for the residues resulting from treatment of ILW. Immobilization agents initially being evaluated for the various residues include cement, urea-formaldehyde, and bitumen although other immobilization agents will be studied. The program also includes development of acceptable test procedures for the final immobilized products as well as development of proposed criteria for storage, transportation, and disposal of the immobilized ILW

Fate and possible nutritional and toxicological significance of methylbromide residues in fumigated cocoa beans. Coordinated programme on isotopic tracer-aided studies on foreign chemical residues in food

International Nuclear Information System (INIS)

Adomako, D.

1975-03-01

Methyl bromide residues in cocoa as a result of fumigation under practical conditions have been studied. Cocoa beans were exposed to 14 C-labelled CH 3 Br for 24 hours at 20-32degC and dosage 23.5 to 28mg/1 of fumigants (moisture content of 6-7%). Whole unroasted beans and their shells and nibs as well as shells and nibs of roasted (105degC for 30 min) beans were extracted separately with toluene (for free CH 3 Br) and the dried residues wet combusted. 14 C-activities were determined by liquid scintillation counting. Total methyl bromide (bound and free) was equivalent 83-98ppm in whole unroasted beans 35 hours after treatment and aeration, and 31, 15 and 10ppm after 7, 42 and 70 days respectively in one set of experiments and 37, 53 and 42ppm after 76, 60 and 51 days in another set. Approximately 80% of the residue occurred in the shells which constitute only 12 to 13% of unroasted beans. 99% of the total residues appeared to be in chemically-bound form. Roasting reduced the total residues by 32 to 62% in nibs and 3.6 to 14% in shells. A striking effect of roasting was the occurrence in roasted nibs of residues as (extractable) carbon-14 (62-82% of the total residues compared to 16.5 - 27% in unroasted nibs). The bound residues behaved as methylated derivatives whilst the volatile fraction behaved as volatile aroma compounds formed by Maillard type reactions from the 14 C-labelled amino acides and sugars

Determination of platinum group metal catalyst residues in active pharmaceutical ingredients by means of total reflection X-ray spectrometry

International Nuclear Information System (INIS)

Marguí, Eva; Queralt, Ignasi; Hidalgo, Manuela

2013-01-01

The control of metal catalyst residues (i.e., platinum group metals (PGMs)) in different stages of the manufacturing processes of the active pharmaceutical ingredients (APIs) and, especially, in the final product is crucial. For API specimens, there are strict guidelines to limit the levels of metal residues based on their individual levels of safety concern. For PGMs the concentration limit has been established at 10 mg/kg in the API. Therefore great effort is currently being devoted to the development of new and simple procedures to control metals in pharmaceuticals. In the present work, an analytical methodology based on benchtop total reflection X-ray fluorescence spectrometry (TXRF) has been developed for the rapid and simple determination of some PGM catalyst impurities (Rh, Pd, Ir and Pt) in different types of API samples. An evaluation of different sample treatments (dissolution and digestion of the solid pharmaceutical samples) has been carried out and the developed methodologies have been validated according to the analytical parameters to be considered and acceptance criteria for PGM determination according to the United States Pharmacopeia (USP). Limits of quantification obtained for PGM metals were in the range of 2–4 mg/kg which are satisfactory according to current legislation. From the obtained results it is shown that the developed TXRF method can be implemented in the pharmaceutical industries to increase productivity of the laboratory; offering an interesting and complementary analytical tool to other atomic spectroscopic methods. - Highlights: • A TXRF method for PGM catalyst residue determination in API samples is presented. • Analysis can be performed using 10 μL of the internal standardized dissolved API. • The method is rapid, simple and suitable according to the USP requirements

Method of producing radioactive technetium-99M

International Nuclear Information System (INIS)

Karageozian, H.L.

1979-01-01

A chromatographic process of producing high purity and high yield radioactive Technetium-99m. A solution containing Molybdenum-99m and Technetium-99m is placed on a chromatographic column and eluted with a neutral solvent system comprising an organic solvent and from about 0.1 to less than about 10% of water or from about 1 to less than about 70% of a solvent selected from the group consisting of aliphatic alcohols having 1 to 6 carbon atoms. The eluted solvent system containing the Technetium-99m is then removed leaving the Technetium-99m as a dry, particulate residue

Methyl bromide residues in fumigated cocoa beans with particular reference to inorganic bromide

International Nuclear Information System (INIS)

Adomako, D.

1976-01-01

Inorganic bromide residues and 14 C-labelled methylated products (expressed as CH 3 Br equivalent) in cocoa beans fumigated with [ 14 C]-methyl bromide have been determined by radiometric and chemical methods. Determination of 14 C by direct combustion in an oxygen chamber followed by liquid scintillation counting confirmed previous findings with respect to the magnitude, distribution and chemical nature of the residues. Although recovery of added bromide was good, the values of total bromide obtained by the chemical method were only half of those estimated from the total residual 14 C-activity. This is attributed to loss of organic (presumably, protein-bound) bromide. In agreement with the total 14 C-labelled residue contents, total bromide in shells was 20 times greater than that in nibs. The low levels of residues in the nib (12ppm as CH 3 Br equivalent, 10ppm Br) and the further reduction of organic residues by roasting suggest that no toxicological and nutritional hazards may be expected from fumigation of cocoa beans with methyl bromide. (author)

Evaluation of NORM residues in the Morro Redondo waterworks, Brazil

International Nuclear Information System (INIS)

Pinto, Michele C.F.; Rocha, Zildete

2007-01-01

Most mineral resources present naturally occurring radioactive material known by the acronym NORM. Some of them, specially those geological material originated from igneous rock present elevated radionuclides concentration. The exploration of these materials may elevate human exposure to the natural ionizing radiation, by removing them from the natural compartment or by increasing the radionuclides concentration in products, by products and more frequently in the industrial residues, these are referred as TENORM Technologically Enhanced NORM. The residues of the waterworks, especially those of the iron and manganese remotion are expected to contain radioactivity concentration due to geological reasons. The paper evaluates the natural radionuclide concentration in the waste water sludge of the iron removing process carried out by the Water Treatment Plant (WTP) - Morro Redondo waterwork operated by Companhia de Saneamento de Minas Gerais - COPASA. Such waterwork supplies drink water for more than 200.000 people, inhabitants of the south part of Belo Horizonte and Nova Lima. The water is extracted from three rock source formations in the iron quadrangle of Minas Gerais, namely Cercadinho, Fechos and Mutuca. The sludges samples analysed have shown values around 300 Bq kg -1 for 226 Ra, in radiological point of view, the most important radionuclide. Values taken from literature were considered - 10.000 Bq kg -1 are not rare, and the ones around 300 Bq kg -1 are normal. (author)

Radioactive waste safety appraisal. An international peer review of the licence application for the Australian near surface radioactive waste disposal facility. Report of the IAEA International Review Team

International Nuclear Information System (INIS)

2004-05-01

Radioactive waste has been generated in Australia for a number of decades from the production and use of radioactive materials in medicine and industry, from the processing of various minerals containing natural radionuclides and from various research activities. It has been decided in the overall interest of safety and security to develop a radioactive waste disposal facility to accommodate the low level and short lived intermediate level waste, which make up the bulk of the waste, other than mining and minerals processing residues. A site selection process has been undertaken and environmental impact statement report prepared and approved. A licence application has been submitted to the national nuclear regulatory authority, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) for siting, construction and operation of the facility. In order to assist the CEO of ARPANSA with his deliberations in this regard a request was made to the IAEA, in terms of its statutory mandate to establish international safety standards for radioactive waste safety and to provide for their application, to undertake an international peer review of the licence application and to advise the CEO accordingly. The outcome and recommendations of this peer review are presented in the report

De minimis applications for alternative disposal of very low level radioactive waste at Duke Power Company

International Nuclear Information System (INIS)

Lan, C.

1986-01-01

Existing NRC regulations provide no minimum level of radioactivity in waste from a licensee's facility that may be disposed of in a manner other than as radioactive waste. With one exception, in 10CFRsection20.306, licensees may dispose of certain levels of tritium and carbon-14 in liquid-scintillation and animal-carcass waste without regard to its radioactivity. In the interim, before specific or generic provisions for disposing of very low level radioactive wastes are adopted through rule making, licensees have another alternative for obtaining approval to dispose of large volumes of materials contaminated with very low levels of radioactivity under provision 10CFRsection20.302(a) ''Method for obtaining approval of proposed disposal procedures.'' This paper provides the experiences of obtaining both NRC and states (North Carolina and South Carolina) approval for disposing of very low-level radioactive wastes from Duke Power Company's nuclear stations. The approved disposal procedures include landfarming of water treatment residues, on-site disposal (burial) of sand and feedwater heaters, and include offsite release for treatment and disposal of sanitary sewage sludge. In summary, users of radioactive materials should not exclude this approach in their quest to reduce the volume of radioactive waste. It is expected that such submittals could provide a data base for further development of generic limits for radioactive wastes

Radioactivity and countermeasures like clean feeding of sheep

International Nuclear Information System (INIS)

2011-01-01

It's been 25 years since the nuclear accident at Chernobyl, but there is still radioactivity remaining in the Norwegian nature. The radioactive cesium-137 is taken up by plants and fungi and transferred to animals on rangelands. In the grazing season of 2010 had 20 000 sheep on Countermeasures like clean feeding to reduce radioactivity levels in the meat before slaughter. Oppland had most sheep on Countermeasures like clean feeding with almost 12 000 animals. Total was paid 2.2 million in compensation to livestock owners in 2010. In the period 1986-2010 is about 2.2 million sheep have been suspended with a charge of approximately NOK 227 million. (AG)

Environmental radioactivity surveillance programme 1988-89

International Nuclear Information System (INIS)

Sequeira, S.; Pollard, D.; Hayden, E.; Dunne, B.; Colgan, P.A.; Cunningham, J.D.

1990-06-01

The Nuclear Energy Board measures radionuclides in air, rainwater, total fallout, drinking water supplies and milk as part of its programme to monitor radioactivity in the Irish environment. The report presents the results of measurements made during 1988 and 1989

Studies on treatment of radioactive animal carcass, (1)

International Nuclear Information System (INIS)

Matsuoka, Osamu; Koizumi, Akira; Fukuda, Satoshi

1979-01-01

A new method of waste treatment of animal carcass contaminated with plutonium was proposed. A multi-step process was designed and tested at a laboratory scale which was composed of the following processes; microwave dehydration, heat decomposition and ashing. Microwave dehydration was found the most adequate as the first step of the treatment because of the negligible release of nonvolatile radioactivity. About 70% of body weight was reduced by microwave dehydration. Dehydrated animal carcass was decomposed by graded electric heating under anaerobic condition. Burnable gas and vapour produced by the heat decomposition were oxidized by passing through a reheating tube with excess air. The exhaust gas had no significant radioactivity. The residue of charred carcass was oxidized by heating with excess air. The weight of final product was up to 8% of original wet weight. The proposed multi-step process provided to be adequate for the waste disporsal of Pu contaminated animal carcass. (author)

Radioactivity. Centenary of radioactivity discovery

International Nuclear Information System (INIS)

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

1997-01-01

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

The 2016-2018 National Plan of Management of Radioactive Materials and Wastes. Final report

International Nuclear Information System (INIS)

2017-01-01

A first document contains the final version of the French National Plan of Management of Radioactive Materials and Wastes (PNGMDR) for the period 2016-2018: principles and objectives (presentation of radioactive materials and wastes, principles to be taken into account to define pathways of management of radioactive wastes, legal and institutional framework, information transparency), the management of radioactive materials (context and challenges, management pathways, works on fast breeder reactors of fourth generation), assessment and perspectives of existing pathways of management of radioactive wastes (management of historical situations, management of residues of mining and sterile processing, management of waste with a high natural radioactivity, management of very short life waste, of very low activity wastes, and low and medium activity wastes), needs and perspectives regarding management processes to be implemented for the different types of radioactive wastes. Appendices to this document contain: a recall of the content of previous PNGMDR since 2007, a synthesis of realisations and researches performed abroad, research orientations for the concerned period, and international agreement on spent fuel and radioactive waste management. A second document, released by the ASN, proposes an environmental and strategic assessment of the plan. A third one and a fourth one contain the opinion of the Environmental Authority on the plan preliminary focus and the answer to the Environmental Authority by the ASN. Finally, a synthesis of the remarks made by the public about the PNGMDR and the answers to these remarks conclude the document

Demolition and removal of radioactively contaminated concrete soil: Aerosol control and monitoring

Energy Technology Data Exchange (ETDEWEB)

Newton, G.J.; Hoover, M.D.; Grace, A.C. III

1995-12-01

From 1963 to 1985, two concrete-lined ponds were used to reduce the volume of radioactive liquids from the Institute`s research programs. Following withdrawal of the {open_quotes}hot ponds{close_quotes} from active use, the residual sludges and plastic liners of the ponds were removed and shipped to a radioactive waste disposal site. From 1987 to 1994, the concrete structures remained undisturbed pending environmental restoration on the site. Restoration began in 1994 and was completed in 1995. Restoration involved mechanical breakup and removal of the concrete structures and removal of areas of contaminated soils from the site. This report describes the design and results of the aerosol control and monitoring program that was conducted to ensure protection of workers and the environment during the restoration process. The aerosol control and monitoring strategy developed for remediation of the ITRI hot ponds was successful both in preventing dispersion of radioactive dusts and in demonstrating that exposures of workers and offsite releases were within statutory limits.

Analysis through indicators of the management of radioactive waste in a radioactive facility

International Nuclear Information System (INIS)

Amador Balbona, Zayda; Argudin Bocourt, William

2013-01-01

The evaluation of the management of radioactive waste in the center of isotopes of the Republic of Cuba is the objective of this work. To do so, all the operations of the management system are evaluated through indicators used by this radioactive facility over a decade ago. Available information is processed from 1996 until 2012. The major waste generators are identified through the indicator of annual generation of each working group by local and by worker and it were analyzed the available store radioactive inventory, the relationship between the variation of annual technological waste volume of waste and the annual total manipulated activity, the relationship generation-declassification and the percent of liquid effluents managed as waste. Indicators of unconditional clearance, as well as the of the gaseous and liquid discharges are presented. It is concluded, with all these indicators, that it is possible to determine where are the causes of the behavior in the generation of radioactive waste if it is an increase of manipulated activity int the places of work or of worker, or improper application of the procedures of collection. It is controlled not only management, but also determines in which aspects can work to achieve the objective of minimizing the formation of these wastes, to be able to reduce the production costs. National shedding environmental regulations are met and the results are acceptable)

Persistence of paraquat in the soil and observations with other herbicides relevant to the theme of bound residues

International Nuclear Information System (INIS)

Hance, R.J.; Byast, T.H.

1984-01-01

Results from three separate experiments that have some relevance to bound residues are reported. In the first, 14 C-labelled paraquat was lost when applied to soil in the field, about 26% of the radioactivity disappearing in 15 months, whereas in laboratory incubation studies there was no loss of radioactivity in one year. Two possible explanations are (i) that there was photolytic decomposition in the field, (ii) the preparation of the soil for the laboratory study upset the microbial ecology of the soil to the detriment of organisms that can degrade paraquat. In an experiment with 14 C-labelled isoproturon, there was an indication that there was slightly more 14 C in the unextractable humin fraction in soil in which wheat plants were grown than in bare soil. Work in the UK, Federal Republic of Germany and in Switzerland has shown that the phytotoxicity of residues of atrazine, carbetamide, chloridazone, propyzamide, simazine, lenacil, monolinuron, linuron, propachlor and methabenzthiazuron can be satisfactorily predicted on the basis of the amount that is extractable with water. This implies that bound residues of these compounds, if they exist, are unlikely to be phytotoxic. (author)

Radii of radioactive nuclei

International Nuclear Information System (INIS)

Mittig, W.; Plagnol, E.; Schutz, Y.

1989-11-01

A new simple direct method for the measurement of the total reaction cross section (σ R ) for several light radioactive nuclei (A≤40) is developed. From that, the reduced strong absorption radii (r o 2 ) are obtained. A comparison is made with data obtained by other techniques. A strong isospin dependence of the nuclear radii is observed. (L.C.) [pt

Determination of Dose from the Disposal of Radioactive Waste Related with TENORM using Residual Radioactivity (RESRAD) Monte Carlo Code

International Nuclear Information System (INIS)

Lwin, Maung Tin Moe; Kassim, Hassan Abu; Amin, Yusoff Mohd.

2008-01-01

The working procedures in the RESRAD for specific evaluations of environmental pollutants are briefly mentioned. The risk of human health associated with Naturally Occurring Radioactive Materials (NORM) who are working in the Malaysian oil and gas industry are analyzed. The sources of NORM and Technologically Enhanced NORM (TENORM) in the oil and gas industry are described. Some measurements for the external and internal effective dose equivalent on the workers will be described. These data are entered into the RESRAD software program and the output reports are taken. Long-term effects of TENORM to the industrial workers are also discussed with graphical illustrations. These results are compared with previous research work within the same field to validate and verify

Study on radioactive waste management scenarios in regular maintenance of a fusion reactor

International Nuclear Information System (INIS)

Someya, Youji; Tobita, Kenji; Yanagihara, Satoshi

2015-01-01

Low-level radioactive waste is generated in large amounts in the operation of a fusion reactor. For this reason, there are needs for the study of radioactive waste management scenarios, as well as the clarification of the function of waste handling facilities in the design phase. This paper describes the management scenarios with a focus on the radioactive waste generated at the time of scheduled maintenance of a nuclear fusion prototype reactor. Based on the temporal change of the residual heat and dose rate of the blanket and diverter, as the furnace equipment associated with induced radioactivity, management period was determined. At this time, the attenuation rate of dose rate and the like of each device are different. So, if maintenance cycle is established for each device and thus storage area is minimized, the control area can be optimized. Based on the 'principle for minimizing radioactive waste,' the reuse of devices is effective in reducing waste. So, in view of a commercial reactor, research and development is required for the establishment of reuse process under high-dose. Since the commitment to radioactive waste is considered to be an important factor in the future for the social acceptance of nuclear fusion reactor development, comprehensive study including the disposal of waste and the reuse of equipment is important. (A.O.)

Marking with radioactive iodine of a plasma substitute and preliminary essays of his kinetic behaviour in rats; Marcacao com radioiodo de um sucedaneo do plasma e ensaios preliminares de seu comportamento cinetico em ratos

Energy Technology Data Exchange (ETDEWEB)

Cova, Wilma Guimaraes

1973-07-01

A blood plasma substitute (Haem accel - PGO), which has as a base a degraded and polymerized gelatin, was labelled with radioactive iodine (I-131) and preliminary essays of its kinetic behavior was done. We have used the labelling method of McFarlaner. The results obtained - radiochemical yield and purity - were favorable. The kinetic behaviour the residual radioactivity studied by measuring the residual radioactivity of the body and excreta in groups of male Wistar rats for a maximum period of 150 hours. These results have shown and excellent correlation for a two components exponential function's adjustment, suggesting therefore a bi compartmental mathematical model. (author)

The effect of commercial processing procedures on {sup 14}C-carbendazim residues in soybean oil and tomato

Energy Technology Data Exchange (ETDEWEB)

Genyuan, Peng; Huaguo, Wang; Mengwen, Qi; Fujun, Wang; Changjiu, Zhou [Laboratory for the Application of Nuclear Techniques, Beijing Agricultural University, Beijing (China)

1994-06-01

Under simulated agricultural practices, soybean plants were treated with {sup 14}C-labelled carbendazim during the blooming stage. The residue in seeds was determined to be 0.067 ppm; corresponding to 0.076 ppm respectively. After subjecting the oil to degumming, alkali treatment, bleaching and deodorization, 53.7% of original radioactivity was removed. Deodorization was the most effect process, removing about 20% of the residue. The concentration of residues in the deodorized oil decreased about 30%. In soybean seed and cake, the residue was mainly present as carbendazim, the concentration of the other metabolites did not exceed 30% of the residue. Tomatoes grown on a field plot were treated with {sup 14}C-carbendazim. After harvest, the tomatoes were processed into tomato juice and canned whole fruit. The magnitude and nature of residues in samples taken at several processing steps were determined to evaluate the effect of commercial processing on removing or eliminating the residues. The results showed that the surface residues on tomato would be removed efficiently by simple washing of tomato. A buffer solution of phosphate had the highest efficiency. Tomato juice contained lower residues than canned whole fruit.

Effects of natural radioactivity on food radioactivity measurement

International Nuclear Information System (INIS)

Ennyu, Atsuhito

2012-01-01

Since the accident of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Company, groups and individuals including local governments, food manufacturers, distribution circles, retail circles, and citizens are eager to measure the radioactivity of food, in order to confirm the safety of food from the concerns about radioactive contamination. The measurement of radioactivity of food is done by quantitatively determining gamma rays due to radioactive cesium that was incorporated into the biosphere cycle after having been released into the environment. As for the radioactivity measurement of food using gamma-ray spectrometry with a potassium iodide scintillation detector, which is very commonly used, this paper describes the handling method of obtained data, the principle of erroneous detection of radioactive cesium and iodine interrupted by natural radionuclides, and countermeasures for it. Major natural radioactivity sources are uranium series and thorium series. This paper explains gamma rays, which are characteristic in the decay process of uranium series and often affect the measurement of radioactive cesium in food and water. (O.A.)

Pesticide residues in locally available cereals and vegetables

International Nuclear Information System (INIS)

Cunanan, S.A.; Santos, F.L.; Bonoan, L.S.

1976-03-01

Vegetable samples (pechay, cabbage, lettuce, green beans and tomatoes) bought from public markets in the Metro Manila area were analyzed for pesticide residues using gas chromatography. The samples analyzed in 1968-69 contained high levels of chlorinated pesticides such as DDT, Aldrin, Endrin, and Thiodan, while in the samples analyzed in January 1976, no chlorinated and organophosphate pesticides were detected. Cereal samples (rice, corn and sorghum) were obtained from the National Grains Authority and analyzed for pesticide residues and bromine residues. Total bromine residues was determined by neutron activation analysis. In most of the samples analyzed, the concentrations of pesticide residues were below the tolerance levels set by the FAO/WHO Committee on Pesticide Residues in Foods. An exception was one rice sample from Thailand, the bromine residue content (110ppm) of which exceeds the tolerance level of 50ppm

Safety aspects in fuel reprocessing and radioactive waste management

International Nuclear Information System (INIS)

Agarwal, K.

2018-01-01

Nuclear energy is used for generation of electricity and for production of a wide range of radionuclides for use in research and development, healthcare and industry. Nuclear industry uses nuclear fission as source of energy so a large amount of energy is available from very small amount of fuel. As India has adopted c losed fuel cycle , spent nuclear fuel from nuclear reactor is considered as a material of resource and reprocessed to recovery valuable fuel elements. Main incentive of reprocessing is to use the uranium resources effectively by recovering/recycling Pu and U present in the spent fuel. This finally leads to a very small percentage of residual material present in spent nuclear fuel requiring their management as radioactive waste. Another special feature of the Indian Atomic Energy Program is the attention paid from the very beginning to the safe management of radioactive waste

Intraoperative ultrasound-assisted enucleation of residual fibroids following laparoscopic myomectomy.

Science.gov (United States)

Hao, Yan; Li, Si-Jing; Zheng, Ping; Wu, Xia; Sheng, Jie; Yuan, Dong-Lan; Zhou, Qi; Wei, Wei; Duan, Ai-Hong; Wu, Qing-Qing; Lu, Dan

2018-05-25

To investigate if intraoperative ultrasounds by laparoscopic and transvaginal ultrasonography (LUS and TVS) could improve enucleating the residual fibroids following laparoscopic myomectomy (LM). From March to December 2016, 78 women with uterine fibroids underwent LM, LUS and TVS were applied to detect residual fibroids and to guide surgeons to enucleate them after the visible fibroids were removed during LM operation. The total number of residual fibroids found by LUS was 140, and the total number found by TVS was 127 following LM (P = 0.03). LUS is statistically superior to TVS in the detection of residual fibroids in the anterior wall (P = 0.004), in the detection of intramural fibroids (P = 0.002), and in the detection of fibroids with a diameter ranging from 0.5 to 1 cm (P = 0.002). According to the total number of enucleated fibroids by LM, patients were divided into three groups (Group 1: 2 to 4, Group 2: 5 to 7 and Group 3: ≥8 fibroid counts). The percentages of patients in each group with residual fibroids at the end of surgery were 22.2%, 51.9% and 66.7% respectively. Both LUS and TVS are beneficial to surgical treatment of fibroids by assisting enucleation of residual fibroids following LM, while LUS is more effective in localizing residual fibroids than TVS. Copyright © 2018 Elsevier B.V. All rights reserved.

Treatment methods and comparative risks of thorium removal from waste residues

Energy Technology Data Exchange (ETDEWEB)

Porter, R.D.; Hamby, D.M.; Martin, J.E.

1997-07-01

This study was done to examine the risks of remediation and the effectiveness of removal methods for thorium and its associated radioactive decay products from various soils and wastes associated with DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). Removal of {sup 230}Th from uranium process residues would significantly reduce the buildup of {sup 226}Ra (half-life of 1600 years), and since {sup 230}Th concentrations at most of the important sites greatly exceed the {sup 226}Ra concentrations, such removal would reduce the accumulation of additional radiation risks associated with {sup 226}Ra and its products; and, if treatment also removed {sup 226}Ra, these risks could be mitigated even further. Removal of {sup 232}Th from thorium process residues would remove the source material for {sup 228}Ra, and since {sup 228}Ra has a half-life of 5.76 years, its control at FUSRAP sites could be done with land use controls for the 30--50 years required for {sup 228}Ra and the risks associated with its decay products to decay away. It must be recognized, however, that treatment methods invariably require workers to process residues and waste materials usually with bulk handling techniques. These processes expose workers to the radioactivity in the materials, therefore, workers would incur radiological risks in addition to industrial accident risks. An important question is whether the potential reduction of future radiological risks to members of the public justifies the risks that are incurred by remediation workers due to handling materials. This study examines, first, the effectiveness of treatment and then the risks that would be associated with remediation.

The status of the radioactive waste management in Korea

International Nuclear Information System (INIS)

Hyun-Soo Park

2001-01-01

In Korea, fourteen nuclear reactors are in operation and by 2015, a total of twenty eight nuclear reactors will be in operation. The current nuclear share occupies about 34.2 % of the total generating capacity of electricity and 46.3 % of the total production of electricity. The active nuclear program causes an inevitable increase in the build-up of radioactive waste, including spent fuel. Therefore, the reliable and effective management of radioactive waste and spent fuel has become a key for the continuous growth of the nuclear power program. By 2000, a total of 84,413 drums of low and intermediate level waste (LILW) shall be generated and it shall drastically increase to 256,520 drums by 2020. Also, the cumulative amount of spent fuel shall reach 4,623 MTU in 2000 and jump to 18,615 MTU by 2020. By the new national planning, AFR storage facilities for spent fuels shall be built by 2016 and a repository for LILW radioactive disposal shall be in operation by 2008. Even though Korea has a ''wait and see'' policy for spent fuel management, several alternative studies on spent fuel management such as DUPIC have been carried out. In parallel, R and D activities to develop the needed technologies for the permanent disposal of spent fuel and HLW have been implemented. In addition, active R and D on the treatment of radioactive waste from the various nuclear fuel cycle as well as the decontamination and the decommissioning of nuclear facilities are in progress. Many of these studies are pursued in the form of international collaboration with prominent overseas organizations. (author)

Status of low-level radioactive waste management in Korea

Energy Technology Data Exchange (ETDEWEB)

Lee, K.J. [Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of). Dept. of Nuclear Engineering

1993-03-01

The Republic of Korea has accomplished dramatic economic growth over the past three decades; demand for electricity has rapidly grown more than 15% per year. Since the first nuclear power plant, Kori-1 [587 MWe, pressurized water reactor (PWR)], went into commercial operation in 1978, the nuclear power program has continuously expanded and played a key role in meeting the national electricity demand. Nowadays, Korea has nine nuclear power plants [eight PWRs and one Canadian natural uranium reactor (CANDU)] in operation with total generating capacity of 7,616 MWe. The nuclear share of total electrical capacity is about 36%; however, about 50% of actual electricity production is provided by these nine nuclear power plants. In addition, two PWRs are under construction, five units (three CANDUs and two PWRs) are under design, and three more CANDUs and eight more PWRs are planned to be completed by 2006. With this ambitious nuclear program, the total nuclear generating capacity will reach about 23,000 MWe and the nuclear share will be about 40% of the total generating capacity in the year 2006. In order to expand the nuclear power program this ambitiously, enormous amounts of work still have to be done. One major area is radioactive waste management. This paper reviews the status of low-level radioactive waste management in Korea. First, the current and future generation of low-level radioactive wastes are estimated. Also included are the status and plan for the construction of a repository for low-level radioactive wastes, which is one of the hot issues in Korea. Then, the nuclear regulatory system is briefly mentioned. Finally, the research and development activities for LLW management are briefly discussed.

Radioactivity Monitoring of the Irish Environment 2007

International Nuclear Information System (INIS)

Fegan, M.; Dowdall, A.; Hanley, O.; Hayden, E.; Kelleher, K.; Long, S.; Smith, V.; Somerville, S.; Wong, J.; Pollard, D.

2008-10-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2007. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the envorinment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. In additiopn, some natural radioactivity exposure pathways are included in the programme including radioactivity in surface and ground drinking water. Radioactivity is present in the environment due to natural oprocesses, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in the Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2007 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at twelve stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows background concentrations of caesium-137 to be measured; another is equipped to

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.

Natural radioactivity levels in different mineral waters from Bulgaria

Energy Technology Data Exchange (ETDEWEB)

Kamenova-Totzeva, R.; Kotova, R.; Tenev, J.; Ivanova, G.; Badulin, V. [Public Exposure Monitoring Laboratory, National Centre of Radiobiology and Radiation Protection, Sofia (Bulgaria)

2013-07-01

The total radioactivity content of 76 mineral waters from different districts in Bulgaria was determined. Natural radioactivity levels resulting from uranium, radium-226, gross alpha and gross beta activity were measured. The results show that the specific activity range from < 0.02 Bq/l to 1.34 (12) Bq/l and from 0.068 (23) Bq/l to 2.60 (50) Bq/l for gross alpha and gross beta activity respectively. For natural Uranium the results vary between 0.020 (5) μg/l and 180(50) μg/l. Radium-226 content is between < 0.03 Bq/l to 0.296 (75) Bq/l. Due to differences in the geological structure of the aquifer, a large difference in values of the radioactive content was mSv/year. Excluding one value, TID do not exceed the permissible limit of 0.10 mSv/year. The correlations between investigated isotopes and Total Dissolved observed. The estimated Total Indicative Dose (TID) ranged from 0.0113 (57) mSv/year to 0.1713 (481) Solvents (TDS) in water were carried out. The results do not show a strong correlation between TDS values and dissolved radionuclides. (author)

Cost-effectivness analysis of total thyroidectomy vs radioiodine for Graves disease

Directory of Open Access Journals (Sweden)

Prokić Anđelka

2013-01-01

Full Text Available Among the patients suffering from hyperthyroidism 60-80% have Graves' disease. The initial therapy of Graves's disease are antithyroid drugs. If the remission is not achieved after 12-18 months, the patients should be directed to surgical treatment or to the therapy with radioactive iodine. The aim of this study was to compare cost/effectiveness ratios for radioactive iodine and total thyroidectomy. The analysis was made using Markov model, from the perspective of Republic Fund for Health Insurance in Serbia. Duration of one cycle in the model is six months, and the time horizon is 30 years. Monte Carlo simulation was performed for 1000 virtual patients as well as the analysis of sensitivity with the variation of parameters ± 50%. For total thyroidectomy the insurance should provide 138.389,72 RSD / 57, 83 QALY i.e. 2.393,04 dinars for one quality-adjusted life year, and for radioactive iodine the insurance should provide 110.043,64 RSD / 57,82 QALY i.e. 1.903,37 dinars for one quality-adjusted life year. This economic analysis showed that radioactive iodine has better ratio of costs to clinical effectiveness as opposed to total thyroidectomy.

U.S. port commerce in radioactive materials

International Nuclear Information System (INIS)

Marti, B.E.

1987-01-01

Much attention has focused on the movement of radioactive materials over land transport systems. On the other hand, maritime flow and associated throughput studies of such substances have been neglected. Although several peaks and troughs are evident between 1972 and 1981, radioactive tonnage moving through U.S. port facilities steadily increasing. In the ten-year period assessed, total radioactive materials handled at U.S. ports expanded by over 19,000 tons, which amounts to almost a 173 percent growth rate. The purpose of this exploratory research is threefold. First, it identifies all U.S. ports which were involved in loading or discharging radioactive materials. The major goal of the identification process is to broaden public awareness of these types of movement. Second, it classifies U.S. seaports based on the magnitude of radioactive tonnage handled. The function of the classification is to impose some order on the varied data, while at the same time categorizing large, medium, and small facilities. Finally, it seeks to verify whether or not a long term trend exists. The objective of the verification process is to ascertain if the distribution of radioactive materials handled at individual ports has remained constant. Port safety and contingency planning are clearly within the purview of coastal zone management. The results of this preliminary research should form a foundation for future studies which compare and evaluate local, state, and federal regulatory policy pertaining to port operations involving radioactive materials, including waste

Measurements of the radioactivity of power plant by-products processed into construction materials

International Nuclear Information System (INIS)

Marcinkowski, S.A.; Dudelewski, H.A.

1992-01-01

The subject of the recycling of residual products comprising, inter alia, fly ash and slags accuring from the combustion of black and brown coal in modern coal dust boilers in the power industry has been topical for a number of years. Numerous discussions and articles in technical periodicals and the daily press have revolved around the problem of the radioactivity of construction materials or construction elements obtained from fly ash or slags of power plant. In Poland, this was a forbidden subject until the publication in 1980 by the Warsaw institute of construction technology of standard no. 234 entitled: 'Recommendations for establishing the natural radioactivity of products processed into construction materials'. (orig.) [de

France / impact of Chernobyl 29 years after. In the Alps, some soils are still 'radioactive wastes'

International Nuclear Information System (INIS)

Chareyron, Bruno

2015-01-01

This report presents and comments sample collections and radioactivity measurements performed in the Mercantour Park, in July 2015 at altitudes between 2.440 and 2.540 meters. It appears that radioactivity at one meter above soil level is still twice higher than normal, and is due to soil residual contamination by caesium 137 which is mainly due to nuclear fallouts associated with the Chernobyl accident. Moreover, in some areas, radioactivity at the soil level presents values which can be tens times higher than natural level. The author therefore outlines that the situation has not evolved a lot since measurements performed at the end of the 1990's. Tables of radiation measurements are provided

A study on radiation-resistance of PIC (polymer-impregnated concrete) for container of conditioning and disposal of low and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Ishizaki, Kanjiro; Sudoh, Giichi; Araki, Kunio; Kasahara, Yuko.

1983-01-01

The radiation-resistance of PIC with test piece was evaluated by irradiation of gamma-rays. All the test pieces had JIS mortar size of 4 x 4 x 16 cm. JIS mortar and concrete were used as specimens. The maximum aggregate size of concrete was 10 mm. The specimens impregnated by MMA (methylmethacrylate) monomer and solution of 10% of PSt (polystyrene) in MMA monomer (MMA .PSt) were polymerized by irradiating for 5 hr at the dose rate of 1 MR (1 x 10 6 Roentgen)/hr. PIC specimens were exposed up to maximum 1000 MR to 60 Co gamma-rays in air and under water which simulate shallow land disposal and deep sea dumping conditions, respectively. The lowering of strength of the PIC exposed to gamma-rays under water was larger than that of the PIC in air. The improving effect of the added PSt on the radiation-resistance was observed. It was observed that the 50 MR-irradiated MMA.PSt-PIC under water, which had the residual compressive strength of 85%, was resistant to gamma-rays. When this residual strength was regarded as a limit of radiation-resistance in air, the limit of MMA and MMA.PSt-PIC were approximately 25 MR and 150 MR, respectively. The lowering of strength was mainly due to the deterioration of MMA polymer in PIC. The total exposure dose for PIC-container was estimated by assuming the conditions about the packaged radioactive wastes, dose rate, container and so on. The total exposure dose on PIC-container for 100 years became roughly 1.25 MR. Therefore, it is estimated that the PIC-containers for conditioning and disposal of low and intermediate level radioactive wastes have a sufficient resistance to radiation arising from wastes. (author)

Penetrative and dislodgeable residue characteristics of 14C-insecticides in apple fruit.

Science.gov (United States)

Mota-Sanchez, David; Cregg, Bert; Hoffmann, Eric; Flore, James; Wise, John C

2012-03-28

Infinite- and finite-dose laboratory experiments were used to study the penetrative and dislodgeable residue characteristics of (14)C-insecticides in apple fruit. The differences in dislodgeable and penetrated residues of three radiolabeled insecticides ((14)C-thiamethoxam, (14)C-thiacloprid, and (14)C-indoxacarb), applied in aqueous solution with commercial formulations, were determined after water and methanol wash extractions. The rate of sorption and extent of penetration into the fruit cuticles and hypanthium of two apple cultivars were measured after 1, 6, and 24 h of treatment exposure, using radioactivity quantification methods. For all three compounds, 97% or more of the treatment solutions were found on the fruit surface as some form of non-sorbed residues. For indoxacarb, sorption into the epicuticle was rapid but desorption into the fruit hypanthium was delayed, indicative of a lipophilic penetration pathway. For the neonicotinoids, initial cuticular penetration was slower but with no such delay in desorption into the hypanthium.

Radioactive waste management

International Nuclear Information System (INIS)

2013-01-01

This eighth chapter presents the radioactive wastes and waste disposal; classification of radioactive wastes; basis requests of the radioactive waste management; conditions for a radioactive waste disposal; registers and inventories; transport of radioactive wastes from a facility to another and the radioactive waste management plan

Deep-well injection of radioactive waste in Russia

International Nuclear Information System (INIS)

Hoek, J.

1998-01-01

In the Russian federation, deep borehole injection of liquid radioactive waste has been established practice since at least 1963. The liquid is injected into sandy or other formations with high porosity, which are isolated by water-tight layers. This technique has also been used elsewhere for toxic liquid waste and residues from mining operations. Deep-well injection of radioactive waste is not currently used in any of the European Commission (EC) countries. In this paper the results of a EC-funded study were presented. The study is entitled 'Measurements, modelling of migration and possible radiological consequences at deep well injection sites for liquid radioactive waste in Russia', COSU-CT94-0099-UK. The study was carried out jointly by AEA Technology, CAG and the Research Institute for Nuclear Reactors (NIIAR) at Dimitrovgrad. Many scientists have contributed to the results reported here. The aims of the study are: Provision of extensive information on the deep-well injection repositories and their use in the former Soviet Union; Provision of a methodology to assess safety aspects of deep-well injection of liquid radioactive waste in deep geological formations; This will allow evaluation of proposals to use deep-well injection techniques in other regions; Support for Russian regulatory bodies through evaluation of the suitability of the sites, including estimates of the maximum amount of waste that can be safely stored in them; and Provision of a methodology to assess the use of deep-well injection repositories as an alternative disposal technique for EC countries. 7 refs

78 FR 45579 - Request for a License to Import Radioactive Waste

Science.gov (United States)

2013-07-29

... NUCLEAR REGULATORY COMMISSION Request for a License to Import Radioactive Waste Pursuant to 10 CFR... Technologies, Inc., Class A Up to a maximum Laundering and Canada June 4, 2013, June 5, 2013, radioactive total of 0.074 decontamination IW032. waste consisting TBq (2 Ci) per of protective 11006100 of corrosion...

Monitoring of radioactivity in 1979

International Nuclear Information System (INIS)

Data are given on the monitoring of radioactive contamination of air and some food stuffe at world locations throughout Western South America, South Pacific and Africa during 1979. Data are included on the total β and γ activity and radionuclide content in air, milk and other environmental samples ( 131 I, 90 Sr, 137 Cs) [fr

Mobility of organic carbon from incineration residues

International Nuclear Information System (INIS)

Ecke, Holger; Svensson, Malin

2008-01-01

Dissolved organic carbon (DOC) may affect the transport of pollutants from incineration residues when landfilled or used in geotechnical construction. The leaching of dissolved organic carbon (DOC) from municipal solid waste incineration (MSWI) bottom ash and air pollution control residue (APC) from the incineration of waste wood was investigated. Factors affecting the mobility of DOC were studied in a reduced 2 6-1 experimental design. Controlled factors were treatment with ultrasonic radiation, full carbonation (addition of CO 2 until the pH was stable for 2.5 h), liquid-to-solid (L/S) ratio, pH, leaching temperature and time. Full carbonation, pH and the L/S ratio were the main factors controlling the mobility of DOC in the bottom ash. Approximately 60 weight-% of the total organic carbon (TOC) in the bottom ash was available for leaching in aqueous solutions. The L/S ratio and pH mainly controlled the mobilization of DOC from the APC residue. About 93 weight-% of TOC in the APC residue was, however, not mobilized at all, which might be due to a high content of elemental carbon. Using the European standard EN 13 137 for determination of total organic carbon (TOC) in MSWI residues is inappropriate. The results might be biased due to elemental carbon. It is recommended to develop a TOC method distinguishing between organic and elemental carbon

Design and device construction for plane tables preparation for counter alpha/beta total; Diseno y construccion de dispositivo para preparacion de planchetas para contador alfa/beta total

Energy Technology Data Exchange (ETDEWEB)

Galicia C, F. J.; Monroy G, F., E-mail: fgalicia82@yahoo.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2014-10-15

This work presents the design and assembly of a device for plane tables preparation for quantification alpha/beta total of radioactive waste samples. The determination of the activity index alpha/beta total is used to detect a wide variety of matrices quickly and the concentration of alpha and/or beta emitters of the contained radionuclides in different samples. In particular, the determination of the activity index alpha and beta total of radioactive wastes involves the digestion of samples in aggressive means that will be evaporated to dryness for its quantification. With the purpose of controlling the emission of corrosive gases during the preparation of the plane tables for the quantification of the index alpha and beta total, was designed and built the device in the Radioactive Waste Laboratory that allows to prepare plane tables for proportional counters in a sure and efficient way. The device is constituted by heating equipment, evaporation cylinder and a gases cleaning system. The self-absorption curve got ready starting from the device. (Author)

Report of radioactivity investigation and research in fiscal year 1984

International Nuclear Information System (INIS)

1985-11-01

National Institute of Radiological Sciences has continuously carried out the investigation and research on the environmental radioactivity level due to the radioactive fallout accompanying nuclear explosion experiments and the radioactive substances released from nuclear facilities and on the safety analysis of those since fiscal year 1959 as a part of the radioactivity investigation and research of Science and Technology Agency. The importance of radioactivity investigation and research increases more accompanying the remarkable progress of the peaceful use of atomic energy and the emphasis placed on the safety analysis of atomic energy utilization. In such situation, in fiscal year 1984, by appropriating the total budget of about 105 million yen, the investigation of the radioactivity level and dose in environment, foods and human bodies, the investigation of the level around nuclear facilities, the business of radioactivity data center, the basic research on the evaluation of the results of radioactivity investigation, the training of environmental radiation monitoring technicians, and the investigation and research on the measurement of and countermeasures to emergency radiation exposure were carried out. In this book, the results of these investigation and research are reported. (Kako, I.)

Controlling the Outcome of Melting Radioactive Sources in Scrap Metal: from Exclusion, Exemption and Clearance towards a 'Codex Metallarius'

Energy Technology Data Exchange (ETDEWEB)

Gonzalez, A.J., E-mail: agonzale@sede.arn.gov.ar [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)

2011-07-15

Orphan radiation sources have been inadvertently incorporated into scrap metal and traces of radioactive residues have appeared in finished metal products causing public anxiety, despair in industry and governmental concern. The international principles of exclusion, exemption and clearance can be used to tackle this problem. They are described in detail, as they are becoming universally established for defining the scope of radiation protection regulations. However, notwithstanding the relevance of these principles, the paper suggests a straightforward professional consensus for discontinuing radiological control of commodities with minute traces of radioactive residues. The consensus should unambiguously specify a generic activity concentration in inedible commodities, including metals, below which radiological control may be effectively relinquished. A subsequent legally binding intergovernmental undertaking could resolve the current regulatory ambiguity, facilitate commercial exchange and ensure adequate public protection. For metals, it might take the form of a 'Codex Metallarius' (similar to the existing Codex Alimentarius for edible commodities) establishing a generic level of radiological acceptability for finished metal products. Furthermore, it is proposed that there should be an international convention to prevent radioactive sources becoming orphaned from regulatory control and then inadvertently appearing in trash and scrap. (author)

Sensitivity and rapidity of the evaporation method for the measurement of the radioactivity of residual water; Sensibilite et rapidite de la methode d'evaporation pour la mesure de la radioactivite d'une eau residuaire

Energy Technology Data Exchange (ETDEWEB)

Cohen, P; Reiffsteck, A; Wormser, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

The authors have used the evaporation method for counting the radioactivity of water polluted to the tolerance limit by Sr{sup 90}. Total duration of the manipulation is 2 hours. (author) [French] Les auteurs ont utilise la methode d'evaporation pour le comptage de la radioactivite d'une eau polluee, a la limite de tolerance, par du {sup 90}Sr. La duree de la manipulation totale est de 2 h. (auteur)

Natural radioactivity in groundwater from the south-eastern Arabian Peninsula and environmental implications

DEFF Research Database (Denmark)

Murad, A.; Zhou, X. D.; Yi, P.

2014-01-01

increase the radioactivity in the groundwater. This conclusion is also supported by the positive correlation between radioactivity and amount of total dissolved solid. Particular water purification technology and environmental impact assessments are essential for sustainable and secure use...

Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

International Nuclear Information System (INIS)

Bell, J.T.; Haas, P.A.; Rudolph, J.C.

1995-01-01

The Oak Ridge National Laboratory (ORNL) is participating in a program to apply a molten salt oxidation (MSO) process to treatment of mixed (radioactive and RCRA) wastes. The salt residues from the MSO treatment will require further separations or other processing to prepare them for final disposal. A bench-scale MSO apparatus is being installed at ORNL and will be operated on real Oak Ridge wastes. The treatment concepts to be tested and demonstrated on the salt residues from real wastes are described

Investigation of natural radioactivity level of the waters in Inner Mongolia

International Nuclear Information System (INIS)

Du Xuelin; Li Wenyuan; Fu Su

1993-01-01

The authors reports the investigation results of natural radioactivity level in rivers, lakes, reservoirs, springs, wells and tap water in Inner Mongolia Autonomous Region. There were totally 326 samples collected from 178 measuring points. The results show that the radioactivity level of varied water bodies of the region was within normal natural background

Sorption-reagent treatment of brines produced by reverse osmosis unit for liquid radioactive waste management

International Nuclear Information System (INIS)

Avramenko, V. A.; Zheleznov, V. V.; Sergienko, V. I.; Chizhevsky, I. Yu

2003-01-01

The results of the pilot plant tests (2002-2003) of the sorption-reagent decontamination of high salinity radioactive waste (brines) remaining after the low-salinity liquid radioactive waste (LRW) treatment in the reverse-osmosis unit from long-lived radionuclides are presented. The sorption-reagent materials used in this work were developed in the Institute of Chemistry FEDRAS. They enable one to decontaminate brines with total salt content up to 50 g/l from long-lived radionuclides of Cs, Sr and Co. At joint application of the reverse-osmosis and sorption-reagent technologies total volume of solid radioactive waste (SRW) decreases up to 100-fold as compared to the technology of cementation of reverse osmosis brines. In this case total cost of LRW treatment and SRW disposal decreases more than 10-fold. Brines decontaminated from radionuclides are then diluted down to the ecologically safe total salts content in water to be disposed of. Tests were performed to compare the efficiency of technologies including evaporation of brines remaining after reverse osmosis process and their decontamination by means of the sorption-reagent method. It was shown that, as compared to evaporation, the sorption-reagent technology provides substantial advantages as in regard to radioactive waste total volume reduction as in view of total cost of the waste management

Study of the spallation residues in the reaction Au (800 MeV/nucleon) + p

International Nuclear Information System (INIS)

Mustapha, Brahim

1999-01-01

As a neutron source, the spallation reaction is of importance for different fields of research and for a possible hybrid reactor. The study of spallation residues, their cross sections and their energetic properties, is necessary for such applications and for a better understanding of this process. Several studies of spallation products were done using spectroscopic methods. Only radioactive nuclides were detected. Aiming at a more precise measurement, covering the whole range of spallation residues, this study was done using the reverse kinematics method. A liquid hydrogen target was irradiated by an 800 MeV/nucleon gold beam. The produced nuclei were detected in flight before any radioactive decay with about 10% precision. Independent cross section were then obtained. Velocity distributions were completely reconstructed. In their present forms, the theoretical calculations based upon the two-step model, 'intra-nuclear cascade' + 'evaporation', are unable to reproduce the whole set of experimental aspects. An inter-comparison using different INC/EVA combinations permitted to identify the more significant points in these calculations. The important behaviour of this codes were examined. Due to compensation effects between both steps, cascade and evaporation, this study did not lead to a definite conclusion. (author)

Using radioactivity

International Nuclear Information System (INIS)

1982-10-01

The leaflet discusses the following: radioactivity; radioisotopes; uses of ionising radiations; radioactivity from (a) naturally occurring radioactive elements, and (b) artificially produced radioisotopes; uses of radioactivity in medicine, (a) clinical diagnostic, (b) therapeutic (c) sterilization of medical equipment and materials; environmental uses as tracers; industrial applications, e.g. tracers and radiography; ensuring safety. (U.K.)